Sample records for stabilized special nuclear

This book gives a special lecture on nuclear reactor, which is divided into two parts. The first part has explanation on nuclear design of nuclear reactor and analysis of core with theories of integral transports, diffusion Nodal, transports Nodal and Monte Carlo skill parallel computer and nuclear calculation and speciality of transmutation reactor. The second part deals with speciality of nuclear reactor and control with nonlinear stabilization of nuclear reactor, nonlinear control of nuclear reactor, neural network and control of nuclear reactor, control theory of observer and analysis method of Adomian.

The modern version of the liquid-drop model (LSD) is compared with the macroscopic part of the binding energy evaluated within the Hartree-Fock- Bogoliubov procedure with the Gogny force and the relativistic mean field theory. The parameters of a liquid-drop like mass formula which approximate on the average the self-consistent results are compared with other models. The limits of nuclearstability predicted by these models are discussed.

This special issue contains papers on the following topics: French nuclear policy; nuclear energy development in Europe; nuclear diversification; Alsthom-Atlantique in the nuclear field; 1981 nuclear electricity generation; EDF siting policy; the N4 model of the 1300 MW series; Creys-Malville; the nuclear industry in Europe; pumps in the nuclear industry [fr

An apparatus for simulating specialnuclear material is provided. The apparatus typically contains a small quantity of specialnuclear material (SNM) in a configuration that simulates a much larger quantity of SNM. Generally the apparatus includes a spherical shell that is formed from an alloy containing a small quantity of highly enriched uranium. Also typically provided is a core of depleted uranium. A spacer, typically aluminum, may be used to separate the depleted uranium from the shell of uranium alloy. A cladding, typically made of titanium, is provided to seal the source. Methods are provided to simulate SNM for testing radiation monitoring portals. Typically the methods use at least one primary SNM spectral line and exclude at least one secondary SNM spectral line.

Yang s theory of economic specialization under increasing returns to scale (Yang 2001) is a formal development of the fundamental Smith-Young theorem on the extent of the market and the social division of labor.In this theory specialization and, thus, the social division of labor is firmly embedded

Based on Nuclear Safety Act (OG 173/03) the State Office for Nuclear Safety (SONS) in 2008 adopted beside Ordinance on performing nuclear activities (OG 74/06) and Ordinance on special conditions for individual activities to be performed by expert organizations which perform activities in the area of nuclear safety (OG 74/06) the new Ordinance on the control of nuclear material and special equipment (OG 15/08). Ordinance on the control of nuclear material and special equipment lays down the list of nuclear materials and special equipment as well as of nuclear activities covered by the system of control of production of special equipment and non-nuclear material, the procedure for notifying the intention to and filing the application for a license to carry out nuclear activities, and the format and contents of the forms for doing so. This Ordinance also lays down the manner in which nuclear material records have to be kept, the procedure for notifying the State administration organization (regulatory body) responsible for nuclear safety by the nuclear material user, and the keeping of registers of nuclear activities, nuclear material and special equipment by the State administration organization (regulatory body) responsible for nuclear safety, as well as the form and content of official nuclear safety inspector identification card and badge.(author)

A nuclear reactor core stabilizing arrangement is described wherein a plurality of actuators, disposed in a pattern laterally surrounding a group of elongated fuel assemblies, press against respective contiguous fuel assemblies on the periphery of the group to reduce the clearance between adjacent fuel assemblies thereby forming a more compacted, vibration resistant core structure. 7 claims, 4 drawing figures

Colombia counts with around 56 centers of Nuclear Medicine, 70 Nuclear Doctors and more of 100 Technologists in this area. The radioisotopes more used are the 131 I and the 99m Tc. The radiological surveillance singular in the country is carried out for external dosimetry, being the surveillance by incorporation of radioactive materials very sporadic in our media. Given the necessity to implement monitoring programs in the incorporation of radionuclides of the occupationally exposed personnel, in the routine practice them routine of Nuclear Medicine, it was implemented a pilot program of Special Monitoring with two centers of importance in the city of Medellin. This program it was carried out with the purpose of educating, to stimulate and to establish a program of reference monitoring with base in the National Program of Monitoring in the radionuclides Incorporation that serves like base for its application at level of all the services of Nuclear Medicine in the country. This monitoring type was carried out with the purpose of obtaining information on the work routine in these centers, form of manipulation and dosage of the radionuclides, as well as the administration to the patient. The application of the program was carried out to define the frequency of Monitoring and analysis technique for the implementation of a program of routine monitoring, following the recommendations of the International Commission of Radiological Protection. For their application methods of activity evaluation were used in urine and in 7 workers thyroid, of those which only two deserve an analysis because they presented important activities. The measures were carried out during one month, every day by means in urine samples and to the most critic case is practiced two thyroid measures, one in the middle of the period and another when concluding the monitoring. To the other guy is practiced an activity count in thyroid when concluding the monitoring period. The obtained result of the

Explosive astrophysical environments invariably lead to the production of nuclei away from stability. An understanding of the dynamics and nucleosynthesis in such environments is inextricably coupled to an understanding of the properties of the synthesized nuclei. In this talk a review is presented of the basic explosive nucleosynthesis mechanisms (s-process, r-process, n-process, p-process, and rp-process). Specific stellar model calculations are discussed and a summary of the pertinent nuclear data is presented. Possible experiments and nuclear-model calculations are suggested that could facilitate a better understanding of the astrophysical scenarios. 39 refs., 4 figs

This report presents details pertaining to an exercise conducted as part of the NKS-B programme using synthetic gamma ray spectra to simulate the type of data that may be encountered in the interception of material potentially containing specialnuclear materials. A range of scenarios were developed involving sources that may or may not contain specialnuclear materials. Gamma spectral data was provided to participants as well as ancillary data and participants were asked, under time constraint, to determine whether or not the data was indicative of circumstances involving specialnuclear materials. The situations varied such that different approaches were required in order to obtain the correct result in each context. In the majority of cases participants were able to correctly ascertain whether or not the situations involved specialnuclear material. Although fulfilling the primary goal of the exercise, some participants were not in a position to correctly identify with certainty the material involved, Situations in which the smuggled material was being masked by another source proved to be the most challenging for participants. (Author)

This report presents details pertaining to an exercise conducted as part of the NKS-B programme using synthetic gamma ray spectra to simulate the type of data that may be encountered in the interception of material potentially containing specialnuclear materials. A range of scenarios were developed involving sources that may or may not contain specialnuclear materials. Gamma spectral data was provided to participants as well as ancillary data and participants were asked, under time constraint, to determine whether or not the data was indicative of circumstances involving specialnuclear materials. The situations varied such that different approaches were required in order to obtain the correct result in each context. In the majority of cases participants were able to correctly ascertain whether or not the situations involved specialnuclear material. Although fulfilling the primary goal of the exercise, some participants were not in a position to correctly identify with certainty the material involved, Situations in which the smuggled material was being masked by another source proved to be the most challenging for participants. (Author)

... COMMISSION SpecialNuclear Material Control and Accounting Systems for Nuclear Power Plants AGENCY: Nuclear...-5028, ``SpecialNuclear Material Control and Accounting Systems for Nuclear Power Plants.'' In DG-5028... Control and Accounting Systems for Nuclear Power Plants.'' DATES: Submit comments by July 16, 2012...

Since their introduction in 1942, sampling inspection procedures have been common quality assurance practice. The U.S. Department of Energy (DOE) supports such sampling of specialnuclear materials inventories. The DOE Order 5630.7 states, Operations Offices may develop and use statistically valid sampling plans appropriate for their site-specific needs. The benefits for nuclear facilities operations include reduced worker exposure and reduced work load. Improved procedures have been developed for obtaining statistically valid sampling plans that maximize these benefits. The double sampling concept is described and the resulting sample sizes for double sample plans are compared with other plans. An algorithm is given for finding optimal double sampling plans that assist in choosing the appropriate detection and false alarm probabilities for various sampling plans

Although the observable universe strictly obeys the laws of quantum mechanics, in many instances, a classical description that either ignores quantum effects entirely or accounts for them at a very crude level is sufficient to describe a wide variety of phenomena. However, when this approximation breaks down, as is often the case for processes involving light nuclei, a full quantum treatment becomes indispensable. This Special Topic in The Journal of Chemical Physics showcases recent advances in our understanding of nuclear quantum effects in condensed phases as well as novel algorithmic developments and applications that have enhanced the capability to study these effects.

The need for greater stability in nuclear regulation is discussed. Two possible approaches for dealing with the problems of new and rapidly changing regulatory requirements are discussed. The first approach relies on the more traditional licensing reform initiatives that have been considered off and on for the past decade. The second approach considers a new regulator philosophy aimed at the root causes of the proliferation of new safety requirements that have been imposed in recent years. For the past few years, the concepts of deregulation and regulatory reform have been in fashion in Washington, and the commercial nuclear power program has not remained unaffected. Many look to these concepts to provide greater stability in the regulatory program. The NRC, the nuclear industry and the administration have all been avidly pursuing regulatory reform initiatives, which take the form of both legislative and administrative proposals. Many of these proposals look to the future, and, if adopted, would have little impact on currently operating nuclear power plants or plants now under construction

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

This paper brings a discussion about the challenges involved in the development of a new kind of nuclear facility in Brazil, a naval base for nuclear submarines, with attention to the licensing process and considerations about the risk-informed decision making application to the licensing process. Initially, a model of such a naval base, called in this work, special industrial facility, is proposed, with its systems and respective sets of basic requirements, in order to make it possible the accomplishment of the special industrial facility support function to the nuclear submarine. A discussion about current challenges to overcome in this project is presented: the challenges due to the new characteristics of this type of nuclear facility; existence of several interfaces between the special industrial facilities systems and nuclear submarine systems in design activities; lack of specific regulation in Brazil to allow the licensing process of special industrial facilities by the nuclear safety authority; and comments about the lack of information from reference nuclear facilities, as is the case with nuclear power reactors (for example, the German Grafenrheinfeld nuclear plant is the reference plant for the Brazilian Angra 2 nuclear plant). Finally, in view of these challenges, an analysis method of special industrial facility operational scenarios to assist the licensing process is proposed. Also, considerations about the application of risk-informed decision making to the special industrial facility activity and licensing process in Brazil are presented. (author)

Experts from around the world are meeting at the IAEA this week for an international symposium on nuclear safeguards, verification, and security. A special session on 2 November focuses on the issue of combating nuclear terrorism. The Special Session, which will bring together experts on nuclear terrorism from around the world, will deal with the following issues: The Psychology of terrorism; Intelligence, police and border protection; Guarding nuclear reactors and material from terrorists and thieves; The threat of nuclear terrorism: Nuclear weapons or other nuclear explosive devices; The threat of nuclear terrorism: Intentional dispersal of radioactive material - Sabotage of fixed installations or transport systems; The Legal Framework: Treaties and Conventions, Laws; Regulations and Codes of Practice; IAEA Nuclear Security and Safety Programmes

Colombia counts with around 56 centers of Nuclear Medicine, 70 Nuclear Doctors and more of 100 Technologists in this area. The radioisotopes more used are the {sup 131} I and the {sup 99m} Tc. The radiological surveillance singular in the country is carried out for external dosimetry, being the surveillance by incorporation of radioactive materials very sporadic in our media. Given the necessity to implement monitoring programs in the incorporation of radionuclides of the occupationally exposed personnel, in the routine practice them routine of Nuclear Medicine, it was implemented a pilot program of Special Monitoring with two centers of importance in the city of Medellin. This program it was carried out with the purpose of educating, to stimulate and to establish a program of reference monitoring with base in the National Program of Monitoring in the radionuclides Incorporation that serves like base for its application at level of all the services of Nuclear Medicine in the country. This monitoring type was carried out with the purpose of obtaining information on the work routine in these centers, form of manipulation and dosage of the radionuclides, as well as the administration to the patient. The application of the program was carried out to define the frequency of Monitoring and analysis technique for the implementation of a program of routine monitoring, following the recommendations of the International Commission of Radiological Protection. For their application methods of activity evaluation were used in urine and in 7 workers thyroid, of those which only two deserve an analysis because they presented important activities. The measures were carried out during one month, every day by means in urine samples and to the most critic case is practiced two thyroid measures, one in the middle of the period and another when concluding the monitoring. To the other guy is practiced an activity count in thyroid when concluding the monitoring period. The obtained

Each 1000 MW(e) reactor in equilibrium contains 15 x 10 9 Ci of radioactivity. To handle this material safety requires an extremely high level of expertise and commitment - in many respects, an expertise that goes beyond what is demanded of any other technology. If one grants that nuclear engineering is more demanding than other engineering because the price of failure is greater, one must ask how can we inculcate into the coming generations of nuclear engineers a full sense of the responsibility they bear in practising their profession. Clearly a first requirement is that all elements of the nuclear community -utility executives, equipment engineers, operating engineers, nuclear engineers, administrators - must recognize and accept the idea that nuclear energy is something special, and that therefore its practitioners must be special. This sense must be instilled into young nuclear engineers during their education. A special responsibility therefore devolves upon nuclear engineering educators: first, to recognize the special character of their profession, and second, to convey this sense to their students. The possibility of institutionalizing this sense of responsibility by establishing a nuclear Hippocratic Oath or special canon of ethics for nuclear engineers ought to be discussed within the nuclear community. (author)

State-of--the-art spectroscopy of nuclei far from stability has achieved an extraordinary level of sophistication and detail in the last ten years. In principle, if a state can be populated, it can be characterized by its energy, spin, parity, and major decay paths. Sometimes its lifetime can be measured. In practice, one is confronted with enormous complexity. To convert raw spectroscopic data into nuclear structure data involves a complex process of disentangling gamma rays and conversion electrons into decay schemes. Specifically, coincidence techniques, especially coincidence intensities, play a crucial role in this process. Recent examples and methods from work done at UNISOR are presented

This report of unclassified Inventory Difference (ID's) covers the twelve months from April 1, 1989 through March 31, 1990 for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic specialnuclear material. Classified information is not included in this report. This classified information includes data for the Rocky Flats and Y-12 nuclear weapons production facilities or facilities under ID investigation. However, classified ID data from such facilities receive the same scrutiny and analyses was the included data. The data in this report have been prepared and reviewed by DOE contractors, field offices, and Headquarters. When necessary, special investigations have been performed in addition to these reviews: This ID data, explanations, reviews, and any additional special investigations, together with the absence of physical indications of any theft attempt, support a finding that no theft or diversion of significant quantities of strategic specialnuclear material has occurred in DOE facilities during the twelve-month period covered by this report

Securing human resources is important for the sustainable development of research, development and utilization of nuclear energy. However, concerns have been raised over the maintenance of human resources due to the decline of public and private investment in research and development of nuclear energy in recent years. To that end, it is essential for the workplace in the field of nuclear energy to be engaging. This special feature article introduced the Government's fund program supporting universities and vocational colleges to develop human resources in the area of nuclear energy. Electric utilities, nuclear industries, nuclear safety regulators and related academia presented respective present status and issues of nuclear energy personnel training with some expectations to the program to secure human resources with professional qualifications. (T. Tanaka)

Construction is a very important stage in the course of realization of Nuclear Power Projects and as much care has be devoted to this stage as to the planning and engineering stages. While the setting up of nuclear power projects used to take over seven years in the past, the time period has now been considerably reduced to about five years with advancements in construction engineering, project management and design techniques, on the basis of new initiatives from the owner agency, Nuclear Power Corporation of India. In this article, the constructional aspects of the specialized structures for nuclear power generation are looked into. (author)

Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country,and technical assistance for domestic end-users using INIS database. Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB, INIS online database, INIS SDI service, and non-conventional literature delivery services. INIS2 DB Host site in Korea has serviced users of domestic and INIS member countries. In order to maintain the same data as Vienna center, the data update process has been performed. Also, publicity information activities were performed by many ways. To construct digital information infrastructure, we changed web server of NUCLIS21 and upgraded information management manager system and constructed full text DB on research and technical reports. Also we collected web DB, digital journals and so on and made an effort on operation of knowledge management system and research documents management. We have inputted over 3,000 records per year since 2002 and the input amount this year has reached 3,738 records. In order to input the comprehensive domestic publication related to nuclear energy, and rise in position of the national center, it is necessary to continue efforts and support budgets. We expect the INIS2 DB Host site will make a contribution to the improvement of productivity in the nuclear energy research as well as the diffusion of information about nuclear energy. We provided users with stable services changing web server of NUCLIS21. Also we contributed to the improvement of librarians' productivity by upgrading information management manager system and provided users with services of web DB, digital journals and so on

Domestic INIS project has carried out various activities on supporting a decision-making for INIS Secretariat, exchanges of the statistical information between INIS and the country, and technical assistance for domestic end-users using INIS database. Based on the construction of INIS database sent by member states, the data published in the country has been gathered, collected, and inputted to INIS database according to the INIS reference series. Using the INIS output data, it has provided domestic users with searching INIS CD-ROM DB, INIS online database, INIS SDI service, and non-conventional literature delivery services. INIS2 DB Host site in Korea has serviced users of domestic and INIS member countries. In order to maintain the same data as Vienna center, the data update process has been performed. Also, publicity information activities were performed by many ways. To construct digital information infrastructure, we changed web server of KORNIS21 and we reconstruct digital library system as separation of KAERI network system. We constructed patent trend analysis system and new SDI service system. Also we collected Web DB, digital journals and so on and made an effort on operation of knowledge management system and research documents management. We have inputted over 4,000 records per year since 2009 and the input amount this year has reached 4,284 records. In order to input the comprehensive domestic publication related to nuclear energy, and rise in position of the national center, it is necessary to continue efforts and support budgets. We expect the INIS2 DB Host site will make a contribution to the improvement of productivity in the nuclear energy research as well as the diffusion of information about nuclear energy. We provided users with stable services changing web server of KORNIS21. Also we contributed to the improvement of researcher's productivity by constructing patent trend analysis system, new SDI service system and provided users with services

The American Nuclear Society (ANS) Special Committee on Nuclear Nonproliferation (SCNN) believes that to reverse current trends, U.S. policy must revisit the fundamental premise of Atoms for Peace: A collaborative nuclear enterprise enhances rather than diminishes national security. To accomplish this, the U.S. Government must develop an integrated policy on energy, nuclear technology, and national security. The policy must recognize that these are interrelated and that an integrated policy will require substantial investments in nuclear research and development and in nuclear education. This paper describes the current activities of the SCNN to heighten awareness of nonproliferation issues for decision makers and ANS members, and alert them to the need for action to resolve these concerns. (author)

This twentieth periodic semiannual report of unclassified Inventory Differences (ID's) covers the second six months of fiscal year 1986 (April 1, 1986, through September 30, 1986) for all key Department of Energy (DOE) and DOE contractor operated facilities possessing strategic specialnuclear materials. Data for the Rocky Flats and Y-12 nuclear weapons production facilities are not included in the report in order to protect classified nuclear weapons information; however, classified ID data from these facilities receive the same scrutiny and analyses as the unclassified data

A series of thermal analyses have been completed for ten storage can configurations representing various cases of materials stored in F-Area. The analyses determine the temperatures of the cans, the specialnuclear material, and the air sealed within the cans. Analyses to aid in understanding the effect of oxide accumulation and metal aging on temperatures are also included.

An overview will be given discussing signatures associated with specialnuclear materials acquired using both active and passive diagnostic techniques. Examples of how technology advancements have helped improve diagnostic capabilities to meet the challenges of today’s applications will be discussed.

... material control and accounting (MC&A) system that will achieve the following performance objectives: (1... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special... COMMISSION (CONTINUED) MATERIAL CONTROL AND ACCOUNTING OF SPECIALNUCLEAR MATERIAL SpecialNuclear Material...

This report presents principles and guidelines for sampling nuclear materials to measure chemical and isotopic content of the material. Development of sampling plans and procedures that maintain the random and systematic errors of sampling within acceptable limits for SNM(SpecialNuclear Materials) accounting purposes are emphasized

This report assesses the job-relatedness of specialized educational programs for licensed nuclear reactor operators. The approach used involved systematically comparing the curriculum of specialized educational programs for college credit, to academic knowledge identified as necessary for carrying out the jobs of licenses reactor operators. A sample of eight programs, including A.S. degree, B.S. degree, and coursework programs were studied. Subject matter experts in the field of nuclear operations curriculum and training determined the extent to which individual program curricula covered the identified job-related academic knowledge. The major conclusions of the report are: There is a great deal of variation among individual programs, ranging from coverage of 15% to 65% of the job-related academic knowledge. Four schools cover at least half, and four schools cover less than one-third of this knowledge content; There is no systematic difference in the job-relatedness of the different types of specialized educational programs, A.S. degree, B.S. degree, and coursework; and Traditional B.S. degree programs in nuclear engineering cover as much job-related knowledge (about one-half of this knowledge content) as most of the specialized educational programs

In order to assess potential benefits of nuclear power with regard to its characteristics of fuel supply stability, the following three aspects are valuated under the Japanese energy and electricity mix: a) economic stability; i.e. nuclear power's contribution to the whole energy and electricity mix in terms of resistance to fluctuation and/or fuel price hikes, b) procurement stability; i.e. natural uranium, the raw fuel material for nuclear power generation, is being imported from more reliable sources through adequately diverse markets than in the cases of oil and natural gas, and, c) passive reserve effect; i.e. fuel materials as running stocks at power stations and fuel service facilities could maintain nuclear power generation running for a certain duration under unexpected disruption of fuel supply. (author)

A liquid volume calibration instrument using a nonconventional technique was needed for the sophisticated plutonium processing facility nearing completion at the Rocky Flats Plant of Rockwell International. It features displacement pistons standardized by dimensional inspection and uses automatic microprocessor control to provide validity checks and a complete data record. The instrument calibrates remote SpecialNuclear Material (SNM) tankage of special design under program control but retains alternate operation modes and the ability to operate in general environments. Calibration data produced on punched paper tape is directly entered into an associated data base which provides analytical treatment in accordance with ANSI N15.19-1975, ''Volume Calibration Techniques for Nuclear Material Control.'' Design considerations, operation, and the results of experiments are discussed. Some error sources are evaluated and composite advantages in the calibration of process tankage are given with emphasis on tank volume reliability for SNM measurements

The last decades brought impressive progress in synthesizing and studying properties of nuclides located very far from the beta stability line. Among the most fundamental properties of such exotic nuclides, the ones usually established first are the half-life, possible radioactive decay modes...... state. A review of the decay modes occurring close to the limits of stability is presented. The experimental methods used to produce, identify, and detect new species and their radiation are discussed. The current theoretical understanding of these decay processes is reviewed. The theoretical...... description of the most recently discovered and most complex radioactive process—the two-proton radioactivity—is discussed in more detail....

A Nuclear Hybrid Energy System (NHES) uses a nuclear reactor as the basic power generation unit, and the power generated is used by multiple customers as combinations of thermal power or electrical power. The definition and architecture of a particular NHES can be adapted based on the needs and opportunities of different localities and markets. For example, locations in need of potable water may be best served by coupling a desalination plant to the NHES. Similarly, a location near oil refineries may have a need for emission-free hydrogen production. Using the flexible, multi-domain capabilities of Modelica, Argonne National Laboratory, Idaho National Laboratory, and Oak Ridge National Laboratory are investigating the dynamics (e.g., thermal hydraulics and electrical generation/consumption) and cost of a hybrid system. This paper examines the NHES work underway, emphasizing the control system developed for individual subsystems and the overall supervisory control system.

A principle possibility of applying the vibrational stabilization method to nuclear reactors is studied. The problem of securing the stability of nuclear reactor operation steady-state regimes is one of the central ones in dynamics theory and nuclear reaction operation experience. In particular, the problem of xenon oscillation suppressing in a reactor, occuring as a result of steady-state regime instability is urgent. Investigation is conducted using the simpliest reactor model, repesenting it as a non-linear object with concentrated parameters. It is proved that vibrational stabilization is achieved by periodic fluctuations of the control rod positions in the reactor core and boric acid concentration in the coolant with period 1s 4 s. In practice stabilization is effective, when the steady-state regime is located near the stability boundary, which appears to be dangerous, i.e. self-oscillations with inadmissibly high amplitude occure in the reactor

This report outlines some of the nuclear structure topics discussed at the Los Alamos Workshop on the Science of Intense Radioactive Ion Beams (RIB). In it we also tried to convey some of the excitement of the participants for utilizing RIBs in their future research. The introduction of radioactive beams promises to be a major milestone for nuclear structure perhaps even more important than the last such advance in beams based on the advent of heavy-ion accelerators in the 1960's. RIBs not only will allow a vast number of new nuclei to be studies at the extremes of isospin, but the variety of combinations of exotic proton and neutron configurations should lead to entirely new phenomena. A number of these intriguing new studies and the profound consequences that they promise for understanding the structure of the atomic nucleus, nature's only many-body, strongly-inteacting quantum system, are discussed in the preceeding sections. However, as with any scientific frontier, the most interesting phenomena probably will be those that are not anticipated--they will be truly new

In this paper, a new type of information available in ENDF is discussed. During a consistency check of the evaluated nuclear data library ENDF/B-VII.0 performed at the Nuclear Data Subdivision of the Institute for Advanced Studies, the size of the files for some materials drew the attention of one of the authors. Almost 94 % of all available information for these specialnuclear materials is used to represent the beta-delayed gamma rays following fission. This is the first time this information is included in an ENDF version. (author)

Category 1 and 2 SpecialNuclear Materials (SNM) require storage in vault or vault type rooms as specified in DOE orders 5633.3A and 6430.1A. All category 1 and 2 SNM in dry storage on the Hanford site that is managed by Westinghouse Hanford Co (WHC) is located in the 200 West Area at Plutonium Finishing Plant (PFP) facilities. This document provides current and projected SNM vault inventories in terms of storage space filled and forecasts available space for possible future storage needs

An absolute nondestructive method for quantitative measurement of uranium concentration and enrichment in specialnuclear materials is proposed. The method uses intrinsic calibration and portable instrumentation and the particularly suitable for IAEA safequards applications. The intrinsic calibration accumulates the positive experience of the previous measurements and the results will be continuously improving. It is possible to measure standards in laboratories and use the results for analysis at different time and places. The tests show a good agreement with known classical methods and better results in some cases

The nuclear modernization programme, offensive and defensive, now being implemented or seriously proposed by the Western nuclear states and the Soviet Union pose critical problems for the stability of the European and global nuclear balance. The Reagan administration's Strategic Defence Initiative (SDI) and the dramatic growth of British and French nuclear capabilities add new strains on the arms race now underway between the superpowers. Current and emerging instabilities must be addressed promptly along a broad political front, within and outside the framework of the Atlantic Alliance, before they further split the alliance and damage efforts---principally those being pursued at Geneva in the superpower arms control talks---to manage the nuclear balance and the conflicts that divide the two blocs in Europe and elsewhere. The first part of this paper diagnoses the disturbing elements of the evolving nuclear environment which promotes instability. The second suggests an approach -- complex bilateralism -- that might be employed to bring these destabilizing trends under control to promote the development of more coherent, cohesive, and mutually confident alliance strategic policies than exist today and to enhance East-West stability

The application of radiation in human health, for both diagnosis and treatment of disease, is an important component of the work of the IAEA. The responsibility for the increasingly technical aspects of this work is undertaken by the medical physicist. To ensure good practice in this vital area, structured clinical training programmes are required to complement academic learning. This publication is intended to be a guide to the practical implementation of such a programme for nuclear medicine. There is a general and growing awareness that radiation medicine is increasingly dependent on well trained medical physicists who are based in a clinical setting. However an analysis of the availability of medical physicists indicates a large shortfall of qualified and capable professionals. This is particularly evident in developing countries. While strategies to increase educational opportunities are critical to such countries, the need for guidance on structured clinical training was recognized by the members of the Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology (RCA) for the Asia-Pacific region. Consequently, a technical cooperation regional project (RAS6038) under the RCA programme was formulated to address this need in this region by developing suitable material and establishing its viability. Development of a clinical training guide for medical physicists specialising in nuclear medicine was started in 2009 with the appointment of a core drafting committee of regional and international experts. The publication drew on the experience of clinical training in Australia, Croatia and Sweden and was moderated by physicists working in the Asian region. The present publication follows the approach of earlier IAEA publications in the Training Course Series, specifically Nos 37 and 47, Clinical Training of Medical Physicists Specializing in Radiation Oncology and Clinical Training of Medical Physicists

In the frame of the French trans-governmental R and D program against chemical, biological, radiological, nuclear and explosives (CBRN-E) threats, CEA is studying the detection of SpecialNuclear Materials (SNM) by neutron interrogation with fast neutrons produced by an associated particle sealed tube neutron generator. The deuterium-tritium fusion reaction produces an alpha particle and a 14 MeV neutron almost back to back, allowing tagging neutron emission both in time and direction with an alpha particle position-sensitive sensor embedded in the generator. Fission prompt neutrons and gamma rays induced by tagged neutrons which are tagged by an alpha particle are detected in coincidence with plastic scintillators. This paper presents numerical simulations performed with the MCNP-PoliMi Monte Carlo computer code and with post processing software developed with the ROOT data analysis package. False coincidences due to neutron and photon scattering between adjacent detectors (cross talk) are filtered out to increase the selectivity between nuclear and benign materials. Accidental coincidences, which are not correlated to an alpha particle, are also taken into account in the numerical model, as well as counting statistics, and the time-energy resolution of the data acquisition system. Such realistic calculations show that relevant quantities of SNM (few kg) can be distinguished from cargo and shielding materials in 10 min acquisitions. First laboratory tests of the system under development in CEA laboratories are also presented.

We develop the real stabilization method within the framework of the relativistic mean-field (RMF) model. With the self-consistent nuclear potentials from the RMF model, the real stabilization method is used to study single-particle resonant states in spherical nuclei. As examples, the energies, widths, and wave functions of low-lying neutron resonant states in 120 Sn are obtained. These results are compared with those from the scattering phase-shift method and the analytic continuation in the coupling constant approach and satisfactory agreements are found

Beta decay data of nuclei far from stability are one of the most important nuclear physics input for the understanding of the element systhesis in the universe and determination of the age of the universe from cosmochronometers and by the latter have implications also for cosmology. The present status of theoretical predictions of beta decay far from stability will be reviewed and the impact on the above astrophysical questions will be outlined. First results of second generation microscopic calculations of β F half lives, which are at present in progress, will be presented. (orig.)

These are slides on specialnuclear material gamma-ray signatures for reachback analysts for an LSS Spectroscopy course. The closing thoughts for this presentation are the following: SNM materials have definite spectral signatures that should be readily recognizable to analysts in both bare and shielded configurations. One can estimate burnup of plutonium using certain pairs of peaks that are a few keV apart. In most cases, one cannot reliably estimate uranium enrichment in an analogous way to the estimation of plutonium burnup. The origin of the most intense peaks from some SNM items may be indirect and from ‘associated nuclides.' Indirect SNM signatures sometimes have commonalities with the natural gamma-ray background.

Prior to April 2007, acceptance and performance testing of the various SpecialNuclear Material (SNM) monitoring devices at the Nevada Test Site (NTS) was performed by the Radiological Health Instrumentation department. Calibration and performance testing on the PM-700 personnel portal monitor was performed, but there was no test program for the VM-250 vehicle portal monitor. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no performance test program. In April of 2007, the Material Control and Accountability Manager volunteered to take over performance testing of all SNM portal monitors at NTS in order to strengthen the program and meet U.S. Department of Energy Order requirements. This paper will discuss the following activities associated with developing a performance testing program: changing the culture, learning the systems, developing and implementing procedures, troubleshooting and repair, validating the process, physical control of equipment, acquisition of new systems, and implementing the performance test program

The Central Bureau for Nuclear Measurements is a laboratory whose special aim was the fabrication, analysis and distribution of foils, targets and other samples for nuclear measurements. Preparation and assaying techniques that have been used since 1963 are briefly reviewed

Current operational needs require the deployment of radiation detection equipment with the ability to accurately and reliably identify specialnuclear materials and their byproducts without dependence on cryogenics...

Oxides with the fluorite-type structure are radiation tolerant materials. They are widely used or envisaged in hostile nuclear environments, such as nuclear fuels or inert transmutation matrices for actinide burning. Study of the radiation stability of this class of solids in various radiative fields is of major importance. Two issues which may affect the stability of materials are considered in this work: the production of radiation damage (ballistic contribution); the modification of the matrix composition by doping (chemical contribution). Both contributions may drastically affect the solid stability. Urania and zirconia single crystals were chosen as fluorite-type canonical systems. They were implanted with low-energy inert gases (He or Xe). The damage in-growth, due to both ballistic and chemical contributions, was investigated by in situ RBS/C experiments in the channelling mode and TEM. Two main steps in the disordering kinetics were observed for both inert gases. Relevant key parameters were found to be: the number of displaced lattice atoms created by the slowing-down of energetic ions during the implantation process; the concentration of noble gas atoms in the solid which cause the formation of large stress fields surrounding gas aggregates.

Therapeutic Nuclear Medicine concerns the administration of appropriate amounts of radioactivity of certain isotopes, in order to achieve internal localized irradiation of neoplasmatic cells. Due to the increased level and the specific isotope characteristics of administered radioactivity, special Radiation Protection precautions must be taken. This study addresses such issues, based on national as well as international legislation and guidelines. Application of the principle of optimization is of outmost importance and is based on individual dose planning. The decision about the release of Nuclear Medicine patients after therapy is determined on an individual basis, taking into account patients' pattern of contact with other people, their age and that of persons in the home environment, in addition to other factors. Estimation of the absorbed dose given to the treated organ is based on uptake measurements and other biokinetic data, as well as on the mass of the treated tissue or organ. Concerning pregnant women, the rule of thumb is that they should not be treated, unless the radionuclide therapy is required to save their lives. In that case, the potential absorbed dose and risk to the foetus should be estimated and conveyed to the patient. After radionuclide therapy, a female should be advised to avoid pregnancy for the period of time depending on the specific radionuclide. This is to ensure that the dose to a conceptus/foetus would probably not exceed 1 mGy (the member of the public dose limit). The radiation risk for relatives and caregivers is small and unlikely to exceed the legal dose constraints during the period of the patient's treatment. Solid waste from the patient's stay in hospital is a different matter, and is normally incinerated or held for a period until radioactive decay brings the activity to an acceptable level.

... COMMISSION Constellation Energy; Notice of Docketing of SpecialNuclear Material License SNM-2505 Amendment... June 15, 2009, from Constellation Energy (Constellation) to amend its SpecialNuclear Material License... will remain the same for this action. An NRC review, documented in a letter to Constellation dated July...

This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove SpecialNuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617,Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove SpecialNuclear Material (SNM) Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617, Rev. 0. This project plan is the top-level definitive project management document for PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baselines to manage the execution of the Remove SNM Materials project. Any deviations to the document must be authorized through the appropriate change control process

Paragraph 70.51(e) of 10 CFR Part 70 requires, with certain exceptions stated in the rule, that each licensee authorized to possess more than one effective kilogram of specialnuclear material (SNM) maintain certain procedures. These procedures are to include: (1) records of the quantities of SNM added to or removed from the process; (2) documentation of all transfers of SNM between material-balance areas to show the identity and quantity of SNM transferred; (3) requirements for authorized signatures on each document used to record the transfer of SNM between material-balance areas; and (4) means for control of and accounting for internal transfer documents. Paragraph 70.58(e) requires licensees to establish, maintain, and follow a system for measuring the SNM transferred between material-balance areas and item-control areas. Paragraph 70.58(f) requires that licensees have a program that evaluates and controls the quality of their measurement system. Additionally, all licensees authorized to possess SNM must comply with paragraph 70.51(b) of 10 CFR Part 70. That rule requires licensees to keep records showing, among other things, the inventory of all SNM in their possession and its location. This guide sets forth acceptable methods for controlling and documenting transfers of SNM within a plant site in order to meet the requirements listed above

In the past, acceptance and performance testing of the various SpecialNuclear Material (SNM) monitoring devices at the Nevada Test Site has been performed by the Radiological Health Instrumentation Department. Calibration and performance tests on the PM-700 personnel portal monitor were performed but there was no test program for the VM-250 vehicle portal monitor because it had never been put into service. The handheld SNM monitors, the TSA model 470B, were being calibrated annually, but there was no program in place to test them quarterly. In April of 2007, the Material Control and Accountability (MC and A) Manager at the time decided that the program needed to be strengthened and MC and A took over performance testing of all SNM portal monitoring equipment. This paper will discuss the following activities associated with creating a performance testing program: changing the culture, learning the systems, writing procedures, troubleshooting/repairing, validating the process, control of equipment, acquisition of new systems, and running the program

A novel solution for the detection and smuggling interdiction of specialnuclear materials is presented here consisting of large detector modules which contain superheated emulsions and which are readout with an optical approach. The detectors can be produced to be fully sensitive to prompt fission neutrons and totally insensitive to the interrogation beam, whether X-rays or neutrons below a chosen energy threshold. Therefore, the detectors are able to operate while the selected interrogation beam is on and they will only pick up the signal from fission neutrons. A position-sensitive readout mechanism is used in our design, relying on the scattering of light by neutron-induced bubbles. A beam of coherent light crosses the active area of the detector, and local variations in scattered light due to the presence of bubbles are detected in real time by arrays of silicon planar photodiodes affixed along the whole length of the detector. The system may offer a variety of advantages compared to current approaches, such as the possibility of simultaneous irradiation and detection, i.e. a 100% duty cycle, without requiring complex signal analysis, and high signal-to-noise ratio, minimizing costly nuisance alarms, thanks to its inherent insensitivity to photons.

During the past two decades the improvements in circuit integration have given rise to many new applications in digital processing technology by continuously reducing the unit cost of processing power. Along with this increase in processing power a corresponding decrease in circuit volume has been achieved. Progress has been so swift that new classes of applications become feasible every 2 or 3 years. This is especially true in the application of proven new technology to specialnuclear materials (SNM) safeguard systems. Several areas of application were investigated in establishing the performance requirements for the SNM safeguard system. These included the improvements in material control and accountability and surveillance by using multiple sensors to continuously monitor SNM inventory within the selected value(s); establishing a system architecture to provide capabilities needed for present and future performance requirements; and limiting operating manpower exposure to radiation. This paper describes two selected topics in the application of state-of-the-art, well-proven technology to SNM safeguard system design

This document is appendices D-J for the SpecialNuclear Materials Cutoff Exercise: Issues and Lessons Learned. Included are discussions of the US IAEA Treaty, safeguard regulations for nuclear materials, issue sheets for the PUREX process, and the LANL follow up activity for reprocessing nuclear materials.

This document is appendices D-J for the SpecialNuclear Materials Cutoff Exercise: Issues and Lessons Learned. Included are discussions of the US IAEA Treaty, safeguard regulations for nuclear materials, issue sheets for the PUREX process, and the LANL follow up activity for reprocessing nuclear materials

Some safety aspects of the Angra 2 and 3 nuclear power plants are presented. An analysis of the civil and mechanical project of these nuclear power plant having in view a safety analysis is done. (E.G.) [pt

Weapons-grade uranium and plutonium could be used as nuclear explosives with extreme destructive potential. The problem of their detection, especially in standard cargo containers during transit, has been described as "searching for a needle in a haystack" because of the inherently low rate of spontaneous emission of characteristic penetrating radiation and the ease of its shielding. Currently, the only practical approach for uncovering well-shielded specialnuclear materials is by use of active interrogation using an external radiation source. However, the similarity of these materials to shielding and the required radiation doses that may exceed regulatory limits prevent this method from being widely used in practice. We introduce a low-dose active detection technique, referred to as low-energy nuclear reaction imaging, which exploits the physics of interactions of multi-MeV monoenergetic photons and neutrons to simultaneously measure the material's areal density and effective atomic number, while confirming the presence of fissionable materials by observing the beta-delayed neutron emission. For the first time, we demonstrate identification and imaging of uranium with this novel technique using a simple yet robust source, setting the stage for its wide adoption in security applications.

Full text: The Radiation Protection Program of the Environmental Protection Agencies of countries employ scientists, engineers, statisticians, economists, lawyers, policy analysts, and public affairs professionals amongst others. These professionals aim to protect workers, the general public, and the environment from harmful radiation exposures and to provide the technical basis for radiation protection policies and regulations. Professionals include Health physicists, Bio statistician, Radio chemist, Radio ecologist, Radio biologist etc. With a large proportion of the population of the nuclear workforce of many countries now approaching retirement age, existing power plants of these countries will be hard pressed to find enough qualified professionals to support their operations. The potential shortage of skilled manpower not only affects utilities, but also impacts the entire nuclear infrastructure, including national laboratories, federal and state agencies, nuclear technology vendors and manufacturing companies, nuclear construction companies, and university nuclear engineering departments. Manpower requirements exist in the nuclear power industry, universities and research establishments, hospitals, government departments, general industry e.g. radiography, transport, instrumentation etc., specialist contractors, agencies and consultancies serving radiation protection. India is no exception. India has the world's 12 th largest economy. Assuming India's average growth rate p.a. of more than 5%, total GDP by 2050 will increase substantially which will require proportionate increase of manpower for all industries. Also chance of brain drain is very high from developing countries e.g. from India to developed countries because of much higher pay and better lifestyle as there will be shortage of manpower in developed countries as explained above. With population growth to be stabilized in future in India, the working age population may not increase in the year 2030

The January 2017 special issue of the IEEE Transactions on Nuclear Science (TNS) contains selected papers from the 53rd annual IEEE International Nuclear and Space Radiation Effects Conference (NSREC) held July 11-15, 2016, in Portland, OR, USA. The 2016 IEEE NSREC was sponsored by the IEEE Nuclear and Plasma Sciences Society. 98 of the 104 papers presented in Portland were submitted for consideration for this year's special issue. The papers that appear in this special issue successfully completed the review process before the deadline. A few additional papers may appear in subsequent issues of the Transactions.

A method and a system for detecting the presence of specialnuclear materials in a container. The system and its method include irradiating the container with an energetic beam, so as to induce a fission in the specialnuclear materials, detecting the gamma rays that are emitted from the fission products formed by the fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the specialnuclear materials using the comparison.

... with developing and deploying nuclear weapons. The US, in the past, has refused to provide technical assistance to enhance the safety, security, and stability of proliferating countries' nuclear arsenals-we believe this policy...

conducted by the Institute for Defense Analyses (IDA) under contract DASW01-04-C-0003,Task DC-6-2819, “NuclearStability in Asia ,” for the Defense Threat...review of emerging nuclearstability issues in Asia . Sponsored by DTRA’s Advanced Systems and Concepts Office, this paper is the latest in a...nuclear weapon states in Asia , such that Asia is now the most nuclearized of all continents. 2. The increasing potential for a cascade of

A graded table for terminating or reducing domestic safeguards has been developed for use by programs and facilities within the Department of Energy in decisions regarding the need for or levels of protection of low-grade nuclear materials. Contained in this table are technical criteria which can allow for complete removal of safeguards over many specialnuclear material forms and concentrations of typical low-grade materials either currently located at generating or processing sites and materials which may arise from processing operations related to stabilization and disposition activities. In addition, these criteria include higher concentration levels which may warrant maintaining some level of (albeit reduced) security on low-grade materials while allowing reductions in materials control and accountability requirements. These reductions can range from complete removal of these materials from materials control and accountability requirements such as measurements, physical inventories and recordkeeping, to deferring these measurements and physical inventories until a time that either the material is removed from the site or resubmitted for processing. It is important to note that other conditions contained in current Departmental safeguards and security policy be met prior to safeguards termination or reduction

The purpose of the report was to reveal the scope of the nuclear industry in the south and the importance of the region to the nuclear dream/nightmare. The report was divided into three sections: the first detailed the south's involvement in each phase of the fuel cycle, from uranium mining to waste disposal. The second section focused on the region's private electric utility companies, which use their entrenched political and financial connections to buttress the crumbling support for nuclear power. The third section explored public power agencies purchasing a share of privately built nuclear reactors

Kingdom desired to retain commonality with the United States in order to maintain its close nuclear relationship with Washington as well as to save time...DETERRENT FORCE AND THE U.S.-U.K. SPECIAL RELATIONSHIP by Emily S. Merritt June 2014 Thesis Advisor: David Yost Second Reader: Daniel...COVERED Master’s Thesis 4. TITLE AND SUBTITLE BRITAIN’S NUCLEAR DETERRENT FORCE AND THE U.S.-U.K. SPECIAL RELATIONSHIP 5. FUNDING NUMBERS 6

Nuclear material accounting systems were examined and compared to financial double-entry accounting systems. Effective nuclear material accounting systems have been designed using the principles of double-entry financial accounting. The modified double-entry systems presently employed are acceptable if they provide adequate control over the recording and summarizing of transactions. Strong internal controls, based on principles of financial accounting, can help protect nuclear materials and produce accurate, reliable accounting data. An electronic data processing system can more accurately maintain large volumes of data and provide management with more current, reliable information

Radioactive waste is generated by many different technical and scientific applications. For the past decades, different waste disposal strategies have been considered. Several questions on the waste disposal strategy remain unanswered, particularly regarding the long-term radiotoxicity of minor actinides (Am, Cm, Np), plutonium and uranium. These radionuclides mainly arise from high level nuclear waste (HLW), specific waste streams or dismantled nuclear weapons. Although many countries have opted for the direct disposal of spent fuel, from a scientific and technical point of view it is imperative to pursue alternative waste management strategies. Apart from the vitrification, especially for trivalent actinides and Pu, crystalline ceramic waste forms are considered. In contrast to glasses, crystalline waste forms, which are chemically and physically highly stable, allow the retention of radionuclides on well-defined lattice positions within the crystal structure. Besides polyphase ceramics such as SYNROC, single phase ceramics are considered as tailor made host phases to embed a specific radionuclide or a specific group. Among oxidic single phase ceramics pyrochlores are known to have a high potential for this application. This work examines ZrO 2 based pyrochlores as potential nuclear waste forms, which are known to show a high aqueous stability and a high tolerance towards radiation damage. This work contributes to (1) understand the phase stability field of pyrochlore and consequences of non-stoichiometry which leads to pyrochlores with mixed cationic sites. Mixed cationic occupancies are likely to occur in actinide-bearing pyrochlores. (2) The structural uptake of radionuclides themselves was studied. (3) The chemical stability and the effect of phase transition from pyrochlore to defect fluorite were probed. This phase transition is important, as it is the result of radiation damage in ZrO 2 based pyrochlores. ZrO 2 - Nd 2 O 3 pellets with pyrochlore and defect

When confronting an item that may contain nuclear material, it is urgently necessary to determine its characteristics. Our goal is to provide accurate information with high-con dence as rapidly as possible.

A new parametrization for the phenomenological nuclear level density taking account of the shell and pairing energies of the recent nuclear mass formula of Koura, Tachibana, Uno, and Yamada (KTUY05) is proposed. Such a level density formula is often required to calculate nuclear reaction cross sections for nuclei off-stability, especially for fission systems and astrophysical applications. With the phenomenological level density formula of Gilbert-Cameron with the energy dependent level density parameter of Ignatyuk, a smooth dependence of the asymptotic level density parameter a * on the mass number is obtained. At low energies, systematics for the constant temperature model are also derived by connecting the Fermi gas level density and the discrete level information available for more than 1,000 nuclei. Some comparisons with the discrete level data and the microscopic model are made to validate our approach, and it is concluded that the parametrization obtained can be used for nuclear reaction calculations on stable or unstable nuclei within a reasonable uncertainty. (author)

Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation

Since the present nuclear safety regulation has some legal problems that refer to special issues and contents of regulatory provisions, this report has preformed research on the legal basic theory of nuclear safety regulation to solve the problems. In addition, this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation.

We are living in an age dominated by science and technology. There are probably at present more scientists alive than all those that passed away through the history of humankind. It is certain that science and technology have the possibility of solving the problems of society. However, these problems have not so far been satisfactorily treated and some scientifically ordered society which might be envisaged should hurt the common humanitarian feeling. These are probably the reasons for which a part of the public opinion has lost its trust in science and many people try to find a relief for their anguish in esoteric religions. It seems therefore necessary for a change of attitude on the part of scientists to restore the positive consideration from the society and to be able to contribute to the future evolution of humankind according to a peaceful and harmonious pattern. This short essay will start describing the historical search for solutions through science, will continue by attempting to define the values which should he added to science in the present time, and will end with possible recommendations for scientists in their connection with society, with particular emphasis on the nuclear issue. All that will be considered here refers mainly to natural sciences. Trying to find which are the attitudes of scientists that could contribute to the benefit of society, one may start with the need of feeling love for the scientific achievements they are able to make. Concerning the specific nuclear issue, both civilian and military applications must be considered. The military applications of nuclear energy should be completely prohibited. Scientists may play a relevant role in the elimination of the nuclear weapon possibility in regions of threshold states or with undeclared arsenals. On the way to nuclear-weapon-free world, it will be crucial to convince all or some of the nuclear powers to dismantle their nuclear arsenals. Scientists may make contribution to the

Many studies have been made in France on the use of nuclear heat for district heating. After a brief account of the problems raised by the use of thermal waste from big nuclear power stations, the quantitative and qualitative needs of heating networks are analyzed and the Thermos project described. This is a very robust reactor of the pool type, with an output of 100MW, supplying low-pressure water at 100 deg C. The advantages from the aspects of safety and economy are described, and the present state of the project and its possible developments summarized [fr

This report documents progress on the Los Alamos Nuclear Materials Stabilization and Packaging projects for the third and fourth quarters of fiscal year 1996. It covers development and production activities for the Plutonium Packaging project, the Plutonium Recovery and Stabilization project, and the Uranium Recovery and Stabilization project. In addition, it reports on quality assurance activities for the Plutonium Packaging project

Low order models are used to investigate the influence of integration methods on observed power oscillations of some nuclear reactor simulators. The zero-power point reactor kinetics with six-delayed neutron precursor groups are time discretized using explicit, implicit and Crank-Nicholson methods, and the stability limit of the time mesh spacing is exactly obtained by locating their characteristic poles in the z-transform plane. These poles are the s to z mappings of the inhour equation roots and, except for one of them, they show little or no dependence on the integration method. Conditions for stable power oscillations can be also obtained by tracking when steady state output signals resulting from reactivity oscillations in the s-Laplace plane cross the imaginary axis. The dynamics of a BWR core operating at power conditions is represented by a reduced order model obtained by adding three ordinary differential equations, which can model void and Doppler reactivity feedback effects on power, and collapsing all delayed neutron precursors in one group. Void dynamics are modeled as a second order system and fuel heat transfer as a first order system. This model shows rich characteristics in terms of indicating the relative importance of different core parameters and conditions on both numerical and physical oscillations observed by large computer code simulations. A brief discussion of the influence of actual core and coolant conditions on the reduced order model is presented

... objectives of paragraph (a) of this section, the material control and accounting system must include the... accounting system at least every 24 months, and document management's action on prior assessment... 10 Energy 2 2010-01-01 2010-01-01 false Nuclear material control and accounting for special...

The incidence of anterior cruciate ligament injury has continued to increase over the last two decades. This injury is associated with abnormal gait patterns and osteoarthritis of the knee. In order to accelerate recovery, the introduction of core stability exercises into the rehabilitation program is proposed. The theory underlying the use of core stability exercise relates to the neuroplasticity that follows anterior cruciate ligament injury. Neuroplasticity in lumbar, thoracic, cervical and brain regions diminish activation in the contralateral thalamus, postparietal cortex, SM1, basal ganglia-external globus pallidus, SII, cingulated motor area, premotor cortex, and in the ipsilateral cerebellum and SM1 and increase activation in pre-SMA, SIIp, and pITG, indicating modifications of the CNS. In addition, the neuroplasticity can regulate the movement of trunk muscles, for example, sternocleidomastoid and lower trapezius muscles. Core stability also demonstrates a negative correlation with the incidence of anterior cruciate ligament injury. Therefore, we propose that core stability exercises may improve the rehabilitation of anterior cruciate ligament injuries by increasing core motor control. Specialized core stability exercises aimed at rectifying biomechanical problems associated with gait and core stability may play a key role in the management of anterior cruciate ligament injury.

An analysis by the Congressional Budget Office (CBO) evaluates whether the current one mill fee now charged to nuclear-electricity consumers will adequately finance the waste disposal program. The CBO found that, if the fee is adjusted annually for inflation, it should provide enough revenues to cover all program costs under all nuclear growth forecasts. If the fee is unchanged, however, the fees will be inadequate if inflation exceeds 3% annually. The report suggests two alternatives for fee revision, but makes no recommendations. The alternatives are to increase the fee only at specific intervals or to automatically adjust the fee through indexation. The report examines the effect of delaying the program, cost overruns, and alternative inflation rate and interest rate assumptions. 3 figures, 12 tables

The possibility of a new oil boycott is continuing threat to the European countries: a new oil crisis would put to a severe test not only the economic but also the social system within the community. In the major part of the community power stations cannot be supplied by solar energy and coal fired power stations present a significant environmental burden so that Europe cannot forgo, under any circumstances, the further development of nuclear energy. (orig.) [de

This issue analyses the first consequences of the Fukushima accident at the world level, i.e. impacts which are either already noticeable or predictable. A first article proposes a portrait of Japan (its historical relationship with nature, the cultural education, the role of its bureaucracy, the Japanese business and political worlds) and evokes the nuclear safety organization at the institutional level. It also evokes the different companies involved in nuclear energy production. The second article discusses and comments the environmental and radiological impact of the accident (protection of the inhabitants, environment monitoring, comparison with Chernobyl, main steps of degradation of the reactors, releases in the sea, total release assessment, soil contamination, food contamination, radiation protection). A third article discusses the international impact, notably for the existing or projected power plants in different countries, in terms of public opinion, and with respect to negotiations on climate. The fourth article discusses the reactions of different countries possessing nuclear reactors. The last article questions the replacement of the lost production (that of Fukushima and maybe another power plant) by renewable energies

This eighth periodic semiannual report of inventory differences covers the second six months of fiscal year 1980 (April 1, 1980, through September 30, 1980), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic specialnuclear material. Strategic specialnuclear material is plutonium or uranium-233 or uranium-235 in material whose uranium-235 content is 20 percent or greater (known as highly enriched uranium). A significant quantity is either 2 kilograms of plutonium or uranium-233 or 5 kilograms of uranium-235 in highly enriched uranium or the appropriate weighted combination. All Inventory Differences reported here have been analyzed, investigated when necessary, and resolved. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic specialnuclear material has occurred

A neurofuzzy logic controller (NFLC), which is implemented by using a multilayer neural network with special types of fuzzifier, inference engine and defuzzifier, is applied to the water level control of a nuclear steam generator (SG). This type of NFLC has the structural advantage that arbitrary two-input, single-output linear controllers can be adequately mapped into a set of specific control rules of the NFLC. In order to design a stability-guaranteed NFLC, the stable sector of the given linear gain is obtained from Lyapunov's stability criteria. Then this sector is mapped into two linear rule tables that are used as the limits of NFLC control rules. The automatic generation of NFLC rule tables is accomplished by using the back-error-propagation (BEP) algorithm. There are two separate paths for the error back propagation in the SG. One considers the level dynamics depending on the tank capacity and the other takes into account the reverse dynamics of the SG. The amounts of error back propagated through these paths show opposite effects in the BEP algorithm from each other for the swell-shrink phenomenon. Through computer simulation it is found that the BEP algorithm adequately generates NFLC rule tables according to given learning parameters. (orig.)

The vulnerability analysis methodology developed for fixed nuclear material sites has proven to be extremely effective in assessing associated transportation issues. The basic methods and techniques used are directly applicable to conducting a transportation vulnerability analysis. The purpose of this paper is to illustrate that the same physical protection elements (detection, delay, and response) are present, although the response force plays a dominant role in preventing the theft or sabotage of material. Transportation systems are continuously exposed to the general public whereas the fixed site location by its very nature restricts general public access.

The vulnerability analysis methodology developed for fixed nuclear material sites has proven to be extremely effective in assessing associated transportation issues. The basic methods and techniques used are directly applicable to conducting a transportation vulnerability analysis. The purpose of this paper is to illustrate that the same physical protection elements (detection, delay, and response) are present, although the response force plays a dominant role in preventing the theft or sabotage of material. Transportation systems are continuously exposed to the general public whereas the fixed site location by its very nature restricts general public access

Full text: South African Network for Nuclear Education Science and Technology (SAN NEST) has the objective to develop the nuclear education system in South Africa to a point where suitably qualified and experienced nuclear personnel employed by nuclear science and technology programmes in South Africa are predominantly produced by the South African education system. This is done to strengthen the nuclear science and technology education programmes to better meet future demands in terms of quality, capacity and relevance. To ensure sustainable relevance, it is important to develop special partnerships with industry. This paper describes unique partnerships that were developed with nuclear industry partners. The success of these partnerships has ensured more industry partners to embrace the model which has proven to develop relevant knowledge, support research and provide innovative solutions for industry. (author

Part IIA of the Environmental Protection Act 1990 sets out a regulatory regime for the identification and remediation of land where contamination is causing unacceptable risks to defined receptors. The Environment Agency has a number of regulatory roles under this regime. Where land is designated as a Special Site, as defined in the Contaminated Land (England) Regulations 2000, the Agency will act as the enforcing authority. It is expected that a similar regime will be introduced in Wales during 2001, but the reader should check whether definitions of Special Sites in the Welsh regulations are the same as in the English ones. The Environment Agency's approach to carrying out its regulatory responsibilities is set out in its Part RA Process Documentation,, available on the Agency website (www.environment-agency. gov.uk). This documentation sets out how the Agency intends to carry out its responsibilities under Part IIA of the Environmental Protection Act 1990, which came into force in England on 1 April 2000

The Detection, Surveillance, Verification, and Recovery Group of the Los Alamos Scientific Laboratory Energy Division/Nuclear Safeguards Programs is now utilizing intelligent data-acquisition instrumentation for assay data analysis of specialnuclear material. The data acquisition and analysis are enabled by the incorporation of a number-crunching microprocessor sequenced by a single component microcomputer. Microcomputer firmware establishes the capability for processing the computation of several selected functions and also the ability of instrumentation self-diagnostics

This Decree has for object to establish a National Accounting and Control of Basic Nuclear Materials and Special Fusionable Materials System, under the supervision of the National Council for the Nuclear Industry Development. Its aims are to account nuclear materials, to control nuclear activities, to preserve and control nuclear information, to keep technical relationship with specialized organizations, and to garant nuclear safeguards [es

Research highlights: → Sde2 is essential for telomere silencing. → Sde2 is involved in the maintenance of genomic stability. → Sde2 promotes the recruitment of SHREC, a histone deacetylase complex, to telomeres. -- Abstract: Telomeres, specialized domains assembled at the ends of linear chromosomes, are essential for genomic stability in eukaryotes. The formation and maintenance of telomeres are governed by numerous factors such as telomeric repeats, telomere-binding proteins, heterochromatin proteins, and telomerase. Here, we report Sde2, a novel nuclear protein essential for telomeric silencing and genomic stability in the fission yeast Schizosaccharomyces pombe. A deficiency in sde2 results in the derepression of the ura4 + gene inserted near telomeric repeats, and the noncoding transcripts from telomeric regions accumulate in sde2Δ cells. The loss of Sde2 function compromises transcriptional silencing at telomeres, and this silencing defect is accompanied by increased levels of acetylated histone H3K14 and RNA polymerase II occupancy at telomeres as well as reduced recruitment of the SNF2 ATPase/histone deacetylase-containing complex SHREC to telomeres. Deletion of sde2 also leads to a higher frequency of mitotic minichromosome loss, and sde2Δ cells often form asci that contain spores in abnormal numbers, shapes, or both. In addition, sde2Δ cells are highly sensitive to several stresses, including high/low temperatures, bleomycin, which induces DNA damage, and thiabendazole, a microtubule-destabilizing agent. Furthermore, Sde2 genetically interacts with the telomere regulators Taz1, Pof3, and Ccq1. These findings demonstrate that Sde2 cooperates with other telomere regulators to maintain functional telomeres, thereby preventing genomic instability.

This report covers data for the period from April 1, 1982, through September 30, 1982, and includes accounting corrections for data from earlier periods. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic specialnuclear material has occurred

Aug 25, 2015 ... An integrated mobile system for port security is presented. The system was designed to perform passive measurements of neutrons and -rays to search and identify radioactive and specialnuclear materials as well as for the active investigations by using the tagged neutron inspection technique of suspect ...

This document is the 2nd volume of the three volume set from the SpecialNuclear Materials Cutoff Exercise held at Hanford in 1994. Volume 2 contains Appendices A-C, with Appendices A and B containing a discussion of the design of the PUREX process and Appendix C containing a discussion of the safeguards measures for the PUREX facility.

A systems engineering approach to programmatic risk assessment, derived from the aerospace industry, was applied to various stabilization technologies to assess their relative maturity and availability for use in stabilizingnuclear materials. The assessment provided valuable information for trading off available technologies and identified the at-risk technologies that will require close tracking by the Department of Energy (DOE) to mitigate programmatic risks

This thesis is concerned with nonlinear analyses of BWR stability behaviour, contributing to a deeper understanding in this field. Despite negative feedback-coefficients of a BWR, there are operational points (OP) at which oscillatory instabilities occur. So far, a comprehensive and an in-depth understanding of the nonlinear BWR stability behaviour are missing, even though the impact of the significant physical parameters is well known. In particular, this concerns parameter regions in whi...

Since about half a century passes after the peaceful use of nuclear energy began in Japan, the safety laws and regulations of the nuclear energy becomes difficult to cope enough with the current situation without regulation structure changing. In March 2007, Tokyo University set up nuclear energy legislation study meeting' consisting of members from regulatory bodies, electric utilities, nuclear industries and others. The special feature introduces five opinions obtained through the argument in the meeting. As an example, Law for the Regulations of Nuclear Sources Material, Nuclear Fuel Material and Reactors is applied to basic design about the commercial reactors, but Electric Utilities Industry Law is applied to a detailed design, and different licensing standard is applied in each. Taking the adjustment of licensing standard with unifying these is necessary for efficiency. In addition, current law for the Regulations of Nuclear Sources Material, Nuclear Fuel Material and Reactors regulates according to the businesses such as reactor facilities, fuel fabrication plants and radioactive waste disposal. As for plural businesses, a low procedure and safety measures are demanded every each business. It is also necessary to include structure of the comprehensive licensing that assumed an enterprise running plural businesses. (T. Tanaka)

The nuclear incompressibility as obtained from different sources, from nuclei, high energy nuclear collisions, supernova and neutron stars are briefly reviewed. All these data in general favour a compression modulus, K α ∼ 300 Mev with a minimum uncertainty ∼ 50 MeV. Using a finite rang e density and momentum dependent two-body effective interaction, variation of nucl ear incompressibility with temperature, asymmetry and density is discussed in a non-relativistic mean field approach. The same formalism has also been used to study the limiting temperatures of infinite as well as finite nuclear systems in the astrophysical context as well as in high energy heavy ion collisions. (autho r). 16 refs., 6 figs., 1 tab

Offshore Power Systems (OPS) is designing and manufacturing standardized Floating Nuclear Plants (FNP). The plant utilizes an ice-condenser and dual containment system with a free-standing steel shell welded to the upper deck of the steel platform. The pressure retaining portion of the platform upper deck in the containment area is designated as the containment baseplate. Certain unique loadings and configurations dictate the development of special criteria for the design and analysis of containment and other safety-related structures. Three topics of these special criteria are presented herein: Containment Shell Buckling Criteria; Containment Baseplate Design Criteria; Criteria for Missile Impact on Steel Panels

Offshore Power Systems (OPS) is designing and manufacturing standardized Floating Nuclear Plants (FNP). The plant utilizes an ice-condenser and dual containment system with a free-standing steel shell welded to the upper deck of the steel platform. The pressure retaining portion of the platform upper deck in the containment area is designated as the containment baseplate. Certain unique loadings and configurations dictate the development of special criteria for the design and analysis of containment and other safety related structures. Three topics of these special criteria are presented herein. (Auth.)

This report provides and explains the generally small differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. This report covers data for the period from October 1, 1977, through March 31, 1978, and includes accounting corrections for data from earlier periods. The data and explanations, together with the absence of physical indications of any theft attempt, support a finding that during this period no theft or diversion of a significant amount of strategic specialnuclear material has occurred

An automated delayed neutron counting (DNC) system has been developed at the Royal Military College of Canada (RMC) to enhance nuclear forensics capabilities pertaining to specialnuclear material analysis. The system utilises the SLOWPOKE-2 Facility at RMC as a neutron source and 3 He detectors. System control and data acquisition occur through a LabVIEW platform. The time dependent count rate of the delayed neutron production has been examined for 235 U, using certified reference materials. Experimental validation according to ISO 17025 protocols suggests typical errors and precision of -3.6 and 3.1%, respectively, and a detection limit of 0.26 μg 235 U. (author)

regional powers and great uncertainty about the shape of the world order,”17 In this second nuclear age, “North Korea, Pakistan , and India have joined the...Ballistic Missile treaty, while it was in place, limited the number of interceptors to 100 total missiles at two complexes – the capitol and an ICBM

The Department of Energy (Department) is responsible for safeguarding a significant amount of plutonium, uranium-233 and enriched uranium - collectively referred to as specialnuclear materials - stored in the United States. The Department`s office of Nonproliferation and National Security has overall management cognizance for developing policies for safeguarding these materials, while other Headquarters program offices have {open_quotes}landlord{close_quotes} responsibilities for the sites where the materials are stored, and the Department`s operations and field offices provide onsite management of contractor operations. The Department`s management and operating contractors, under the direction of the Department, safeguard and account for the specialnuclear material stored at Department sites.

Specialnuclear materials vehicle monitors, including gateside vehicle monitors, hand-held personnel-vehicle monitors, and a new tunnel monitor concept for very large vehicles, are discussed. The results of a comparison of effectiveness of monitors for domestic application are presented. The results of calculations and small scale prototype measurements are given for a tunnel-like neutron monitor for monitoring at the perimeter of an enrichment plant subjected to International Safeguards

A serious psychological barrier to acceptance of the concept for achieving the nuclear-weapon-free world is fear of facing the prospect that one or more nations or extremist political groups might develop their own nuclear weapons. Actually this is a question of stability of the nuclear-weapon-free world. From this point of view the most effective system of verification is an absolute necessity. This system must ensure detection of so called undeclared nuclear activity at early stage. Scientists of Russian nuclear centers are working today on solving this problem. This paper is considered to be a comprehensive attempt to analyze the technical and organizational aspects of the problems of transition to a nuclear-weapons-free world, setting aside the difficulties of resolving purely political problems

The CIRENE plant which will undergo preoperational tests in the near future is equipped with a 40 MW(e) Heavy Water moderated Boiling Light Water cooled Reactor (HWBLWR); at the start-up and up to about 30 % of nominal power, the necessary low coolant density is obtained injecting into the core a mixture of liquid and steam. To verify the thermal-hydraulic stability of the plant in this situation, tests have been carried out in a facility simulating two full scale power channels; the system stability has been confirmed in the reference conditions, and is not reduced by even a significant reduction of the liquid flowrate, where a decrease in liquid temperature has some negative effect and steam flowrate has a small influence. (author)

A method and a system for detecting the presence of specialnuclear materials in a suspect container. The system and its method include irradiating the suspect container with a beam of neutrons, so as to induce a thermal fission in a portion of the specialnuclear materials, detecting the gamma rays that are emitted from the fission products formed by the thermal fission, to produce a detector signal, comparing the detector signal with a threshold value to form a comparison, and detecting the presence of the specialnuclear materials using the comparison.

Active interrogation is a vigorous area of research and development due to its promise of offering detection and characterization capabilities of specialnuclear material in environments where passive detection fails. The primary value added by active methods is the capability to penetrate shielding - specialnuclear material itself, incidental materials, or intentional shielding - and advocates hope that active interrogation will provide a solution to the problem of detecting shielded uranium, which is at present the greatest obstacle to interdiction efforts. The technique also provides a unique benefit for quantifying nuclear material in high background-radiation environments, an area important for nuclear material safeguards and material accountancy. Progress has been made in the field of active interrogation on several fronts, most notably in the arenas of source development, systems integration, and the integration and exploitation of multiple fission and non-fission signatures. But penetration of interrogating radiation often comes at a cost, not only in terms of finance and dose but also in terms of induced backgrounds, system complexity, and extended measurement times (including set up and acquisition). These costs make the calculus for deciding to implement active interrogation more subtle than may be apparent. The purpose of this review is thus to examine existing interrogation methods, compare and contrast their attributes and limitations, and identify missions where active interrogation may hold the most promise.

The influence that nuclear power plants and high voltage power systems have on each other when confronted by disturbances in the offsite network may lead, due to dynamic effects, to plant trip. It is therefore necessary to study the disturbances in the network and the effects on plant equipment by means of dynamic simulations which evaluate the unit protection system and the auxiliary services so as to obtain maximum unit availability without jeopardizing its safety. These studies can be conducted since there are models and software tools capable of simulating dynamic behaviour of the electric system, including the excitation systems and specific speed governors obtainment of valid. (author)

Any process involving nuclear interactions gives rise to radioactivity and radiation in various degrees apart from conventional effects like heat, pressure, etc. Vessels and structures containing such processes are subject to various degrees of radioactivity and contamination by liquid, gaseous or particulate radioactive materials coming in contact with the substrate. Thus, in any nuclear environment surfaces require protection against both radioactive contamination and normal corrosion forces. The protective coating should be able to resist the radiation field in which it is placed and also withstand decontamination process for removal of radioactive contamination from the surface as and when required. Radioactive contamination due to any radiochemical operation is objectionable for two reasons: (i) it constitutes a potential radiation hazard to occupants of the facility, and (ii) cross contamination jeoparadizes the validity of the experimental data. The difficulty experienced in decontaminating many materials used in construction of such nuclear or radiochemical facilities has therefore given emphasis to the search for suitable coating matetials. This paper deals with the two special duties expected of paints in such environment, viz., radiation resistance and decontaminability tests in this regard in BARC and examples of actual selections and applications in an Indian nuclear power station. Some areas requiring investigations and serious attention for industrial painting in general and nuclear painting work in particular have been also identified. (author)

Full Text Available The stability analysis of a nuclear reactor is an important aspect in the design and operation of the reactor. A stable neutronic response to perturbations is essential from the safety point of view. In this paper, a general methodology has been developed for the linear stability analysis of nuclear reactors using the lumped reactor model. The reactor kinetics has been modelled using the point kinetics equations and the reactivity feedbacks from fuel, coolant and xenon have been modelled through the appropriate time dependent equations. These governing equations are linearized considering small perturbations in the reactor state around a steady operating point. The characteristic equation of the system is used to establish the stability zone of the reactor considering the reactivity coefficients as parameters. This methodology has been used to identify the stability region of a typical pressurized heavy water reactor. It is shown that the positive reactivity feedback from xenon narrows down the stability region. Further, it is observed that the neutron kinetics parameters (such as the number of delayed neutron precursor groups considered, the neutron generation time, the delayed neutron fractions, etc. do not have a significant influence on the location of the stability boundary. The stability boundary is largely influenced by the parameters governing the evolution of the fuel and coolant temperature and xenon concentration.

Nuclear forensic analysis is a modem science that uses numerous analytical techniques to identify and attribute nuclear materials in the event of a nuclear explosion, radiological terrorist attack or the interception of illicit nuclear material smuggling. The Canadian Department of National Defence has participated in recent international exercises that have highlighted the Nation's requirement to develop nuclear forensics expertise, protocol and capabilities, specifically pertaining to the analysis of specialnuclear materials (SNM). A delayed neutron counting (DNC) system has been designed and established at the Royal Military College of Canada (RMC) to enhance the Government's SNM analysis capabilities. This analytical technique complements those already at RMC by providing a rapid and non-destructive method for the analysis of the fissile isotopes of both uranium (U) and plutonium (Pu). The SLOWPOKE-2 reactor at RMC produces a predominately thermal neutron flux. These neutrons induce fission in the SNM isotopes 233U, 235U and 239Pu releasing prompt fast neutrons, energy and radioactive fission fragments. Some of these fission fragments undergo beta - decay and subsequently emit neutrons, which can be recorded by an array of sensitive 3He detectors. The significant time period between the fission process and the release of these neutrons results in their identification as 'delayed neutrons'. The recorded neutron spectrum varies with time and the count rate curve is unique to each fissile isotope. In-house software, developed by this project, can analyze this delayed neutron curve and provides the fissile mass in the sample. Extensive characterization of the DNC system has been performed with natural U samples with 235 U content ranging from 2--7 microg. The system efficiency and dead time behaviour determined by the natural uranium sample analyses were validated by depleted uranium samples with similar quantities of 235 U resulting in a typical relative error of

... adequacy under Sec. 611 of Public Law 92-574, the ``Noise Control Act of 1972.'' The FAA issues special... specific issues raised in the flight characteristics of an unlimited aerobatic airplane. Therefore, the FAA... positive and, at some points, neutral stability within its flight envelope. Its lateral and directional...

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In bombardments of {sup 248}Cm with {sup 22}Ne the authors discovered two new isotopes, {sup 265}106 and {sup 266}106, by establishing genetic links between {alpha} decays of the 106 nuclides and SF or {alpha} decays of the daughter (grand-daughter) nuclides. For {sup 266}106 they measured E{sub {alpha}}=8.62{+-}0.06 MeV followed by the SF decay of {sup 262}104 for which they measured a half-life value of 1.2{sup +1.0}{sub {minus}0.5} s. For {sup 265}106 they measured E{sub {alpha}}=8.82{+-}0.06 MeV. They estimated {alpha} half-lives of 10-30 s for {sup 266}106 and 2-30 s for {sup 265}106 with SF branches of {approximately}50% or less. The decay properties of {sup 266}106 indicate a large enhancement in the SF stability of this N=160 nuclide and confirm the existence of the predicted neutron-deformed shell N=162.

An important aspect of insider protection in production facilities is the monitoring of the movement of specialnuclear material (SNM) and personnel. One system developed at Sandia National Labs for this purpose is the Personnel and Material Tracking System (PAMTRAK). PAMTRAK can intelligently integrate different sensor technologies and the security requirements of a facility to provide a unique capability in monitoring and tracking SNM and personnel. Currently many sensor technologies are used to track the location of personnel and SNM inside a production facility. These technologies are generally intrusive; they require special badges be worn by personnel, special tags be connected to material, and special detection devices be mounted in the area. Video technology, however, is non-intrusive because it does not require that personnel wear special badges or that special tags be attached to SNM. Sandia has developed a video-based image processing system consisting of three major components: the Material Monitoring-Subsystem (MMS), the Personnel Tracking Subsystem (PTS) and the Item Recognition Subsystem (IRS). The basic function of the MMS is to detect movements of SNM, that occur in user-defined regions of interest (ROI) from multiple cameras; these ROI can be of any shape and size. The purpose of the PTS is to track location of personnel in an area using multiple cameras. It can also be used to implement the two-person rule or to detect unauthorized personnel in a restricted area. Finally, the IRS can be used for the recognition and inventory of SNM in a working area. It can also generate a log record on the status of each SNM. Currently the MMS is integrated with PAMTRAK to complement other monitoring technologies in the system. The paper will discuss the system components and their implementations, and describe current enhancements as well as future work.

This fourteenth periodic semiannual report of Inventory Differences (ID) covers the last six months of fiscal year 1983 (April 1, 1983 through September 30, 1983), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic specialnuclear material (SSNM). Inventory Differences are expected in nuclear material processing and are not, in and of themselves, evidence of lost or stolen material. On the other hand, ID analysis provides valuable information on the effectiveness of the safeguards system's physical protection and material control measures as well as a check on the process controls and material management procedures. ID's outside safeguards control limits or involving a missing SSNM discrete item are investigated. If necessary, an operation may be shut down until an ID is resolved

In the event of a severe accident with core melting in a nuclear power plant, a prerequisite to avoid late containment failure is the stabilization and cooling of the molten core debris. While in newly built Generation III+ nuclear power plants, the design already includes dedicated core melt stabilization measures and systems, core melt mitigation in existing plants is restricted by the already present design features and plant layout. However, also here limited modifications and improvements are possible. In this paper, first the general design requirements for core melt stabilization are outlined. Then the actual implementation of a core melt stabilization system in current Generation III+ nuclear power plants is described, specifically for the AREVA EPR™ reactor and the ATMEA1 reactor. Both solutions combine an initial phase of melt collection in the reactor pit after reactor pressure vessel failure and a later phase with corium spreading and cooling in a lateral core catcher. The paper explains why for these pressurized water reactor plants AREVA utilizes an ex-vessel melt stabilization concept with a dry pit and not in-vessel melt retention with outside reactor pressure vessel flooding. The methodology that is applied to deterministically validate the proper design and functioning of this core melt stabilization system is described. Next, key features of various concepts applicable for the retrofitting of ex-vessel core melt stabilization systems to existing plants are discussed and examples of currently investigated solutions for both boiling and pressurized water reactors are given. The practical applicability of such concepts depends on the specifics of the reactor design, the intended safety targets, and on how well the system fits into the integrated approach for safety improvements. It is emphasized that a core catcher is not a solitary hardware system, but must be designed such that it integrates well into the general plant safety concept and works

Zeta potential (ZP) values were calculated from electrophoresis measurements performed on Fe 3 O 4 and Cu 2 O particles and used with microscope observations to assess the degree of stability of the suspended solids in the acidic and alkaline solvents employed for cleaning nuclear steam generators. In the acidic solvent, the degree of stability proved outstandingly good with a ZP of approximately -352 mV. The EDTA and citric acid constituents of the solvent are potential-determining ions acting as anionic surface-active agents. Nitrogen bubbling and the presence of N 2 H 4 have a stabilizing effect on the suspensions, which increases as the solvent ages. On the other hand, suspensions in the alkaline solvent are unstable, with ZP values between -10 and -30 mV. Surface-active agents of the anionic carboxylate type are far more effective than the non-ionic type for improving stability. (author)

Coupled neutronics-thermal hydraulic codes are used by many utilities, research institutes and regulatory authorities worldwide for performing BWR stability analysis. RAMONA-3 has been established in the industry for quite a long time as a reliable time-domain dynamic code with best performance for predictive calculations. Next generation of codes such as RAMONA-5, SIMULATE-3K and POLCA-T, with advanced two-group neutronics and more detailed plant description and thermal hydraulics models have been introduced. The performance of these codes against the stability measurements performed in cycle 19 at the Swiss nuclear power plant Leibstadt (KKL), a BWR/6 from General Electric, is presented in this paper. Important suppliers of the nuclear industry such as Westinghouse Electric Sweden, AREVA NP Germany, Studsvik Scandpower Inc. USA, and the Swiss research institute PSI have participated in this work. The validation of calculation methods against the KKL stability measurements was considered important by the various organizations for different reasons. Amongst others, Studsvik Scandpower aimed at filling a gap in the SIMULATE-3K stability benchmark database to include a jet pumps driven plant, AREVA NP had to fulfill fuel licensing requirements, and Westinghouse planned to launch POLCA-T parallel to a validation of RAMONA-5 as a production code. PSI cooperated with KKL in stability issues from the very beginning and introduced the stability test project in the framework of NACUSP, a European consortium that aimed for a better understanding of the BWR stability problem. For that purpose, this validation provides an assessment of advanced stability codes for modern BWR core designs. (authors)

Full Text Available AID (Activation Induced Deaminase deaminates cytosines in DNA to initiate immunoglobulin gene diversification and to reprogram CpG methylation in early development. AID is potentially highly mutagenic, and it causes genomic instability evident as translocations in B cell malignancies. Here we show that AID is cell cycle regulated. By high content screening microscopy, we demonstrate that AID undergoes nuclear degradation more slowly in G1 phase than in S or G2-M phase, and that mutations that affect regulatory phosphorylation or catalytic activity can alter AID stability and abundance. We directly test the role of cell cycle regulation by fusing AID to tags that destabilize nuclear protein outside of G1 or S-G2/M phases. We show that enforced nuclear localization of AID in G1 phase accelerates somatic hypermutation and class switch recombination, and is well-tolerated; while nuclear AID compromises viability in S-G2/M phase cells. We identify AID derivatives that accelerate somatic hypermutation with minimal impact on viability, which will be useful tools for engineering genes and proteins by iterative mutagenesis and selection. Our results further suggest that use of cell cycle tags to regulate nuclearstability may be generally applicable to studying DNA repair and to engineering the genome.

Measures to protect specialnuclear materials in West Germany are based on a relatively likely average threat and not on the less-likely but maximum credible threat. The reason is to avoid the costs of maintaining a very high level of security that is seldom needed. The concept of delayed action, which divides the responsibility for security between private protection forces and local police forces, would be insufficient in the event of the maximum credible threat. In principle, sufficient security is possible only when the facilities and transports are constantly protected by a police force large enough to deal with the maximum credible threat without assistance from outside. They must also be adequately armed to avert all possible attackers, and they must be paid by the licensees. The threat of an insider(s) diverting specialnuclear material can be addressed only by strengthening the scope and depth of the checks on applicants and employees and the permanent work controls. It is recognized, however, that such security measures may not be compatible with constitutional civil liberties

The natural dynamic stability time limits were determined for the main types of power set, using a micro-network. By definition, the characteristic feature of natural dynamic stability is that speed governing is in effective, i.e. a constant driving torque is applied to the machine shaft. The time limits give an order of magnitude of the performance to be expected from future power sets connected to the system in the 1980s, for which low-inertia conventional sets running at 3000 rev/min or high-inertia nuclear power sets at 1500 rev/min are envisaged [fr

A systems engineering approach to programmatic risk assessment, derived from the aerospace industry, was applied to various stabilization technologies to assess their relative maturity and availability for use in stabilizingnuclear materials. The assessment provided valuable information for trading off available technologies and identified the at-risk technologies that will require close tracking by the Department of Energy (DOE) to mitigate programmatic risks. This paper presents the programmatic risk assessment methodology developed for the 1995 R and D Plan and updated for the 1996 R and D Plan. Results of the 1996 assessment also are presented (DOE/ID-10561, 1996)

The application of radiation in human health, for both diagnosis and treatment of disease, is an important component of the work of the IAEA. The responsibility for the increasingly technical aspects of this work is undertaken by the medical physicist. To ensure good practice in this vital area, structured clinical training programmes are required to complement academic learning. This publication is intended to be a guide to the practical implementation of such a programme for nuclear medicine. There is a general and growing awareness that radiation medicine is increasingly dependent on well trained medical physicists who are based in a clinical setting. However an analysis of the availability of medical physicists indicates a large shortfall of qualified and capable professionals. This is particularly evident in developing countries. While strategies to increase educational opportunities are critical to such countries, the need for guidance on structured clinical training was recognized by the members of the Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology (RCA) for the Asia-Pacific region. Consequently, a technical cooperation regional project (RAS6038) under the RCA programme was formulated to address this need in this region by developing suitable material and establishing its viability. Development of a clinical training guide for medical physicists specialising in nuclear medicine was started in 2009 with the appointment of a core drafting committee of regional and international experts. The publication drew on the experience of clinical training in Australia, Croatia and Sweden and was moderated by physicists working in the Asian region. The present publication follows the approach of earlier IAEA publications in the Training Course Series, specifically Nos 37 and 47, Clinical Training of Medical Physicists Specializing in Radiation Oncology and Clinical Training of Medical Physicists

The application of radiation in human health, for both diagnosis and treatment of disease, is an important component of the work of the IAEA. The responsibility for the increasingly technical aspects of this work is undertaken by the medical physicist. To ensure good practice in this vital area, structured clinical training programmes are required to complement academic learning. This publication is intended to be a guide to the practical implementation of such a programme for nuclear medicine. There is a general and growing awareness that radiation medicine is increasingly dependent on well trained medical physicists who are based in a clinical setting. However an analysis of the availability of medical physicists indicates a large shortfall of qualified and capable professionals. This is particularly evident in developing countries. While strategies to increase educational opportunities are critical to such countries, the need for guidance on structured clinical training was recognized by the members of the Regional Cooperative Agreement for Research, Development and Training related to Nuclear Science and Technology (RCA) for the Asia-Pacific region. Consequently, a technical cooperation regional project (RAS6038) under the RCA programme was formulated to address this need in this region by developing suitable material and establishing its viability. Development of a clinical training guide for medical physicists specialising in nuclear medicine was started in 2009 with the appointment of a core drafting committee of regional and international experts. The publication drew on the experience of clinical training in Australia, Croatia and Sweden and was moderated by physicists working in the Asian region. The present publication follows the approach of earlier IAEA publications in the Training Course Series, specifically Nos 37 and 47, Clinical Training of Medical Physicists Specializing in Radiation Oncology and Clinical Training of Medical Physicists

This special research project was started in 1978 as five-year plan. The purposes are to clarify the aspect of radiation exposure in human bodies due to the radioactive substances brought into the environment regarding the utilization of atomic energy, its mechanism and various factors affecting it, and to contribute to the evaluation of exposure dose, the reduction of radiation exposure, the conditions of locating nuclear facilities and the improvement of the method of disposing radioactive wastes. In addition to the fields treated in the previous special research project, the experimental research concerning the metabolism of environmental radioactive nuclides in bodies, namely the problem of the peculiarity of radioactive nuclide kinetics in infants and fetuses different from adults and the possibility of causing the changes in the intake and metabolism of nuclides in foods by the difference in their states of existence, was newly included. Also the research concerning the method of evaluating the absorbed dose in human organs at the time of irradiation outside and inside bodies in a new subject. Accordingly, this special research project is composed of (1) the research concerning the radionuclide kinetics in the environment, (2) the research concerning the radionuclide kinetics in bodies, (3) the research concerning the measurement and evaluation of dose absorbed in internal organs due to environmental radiation, and (4) the research concerning the monitoring of low level environmental radiation. The results obtained so far are reported. (Kako, I.)

This sixteenth periodic semiannual report of Inventory Differences (ID) covers the last six months of fiscal year 1984 (April 1, 1984, through September 30, 1984), for the Department of Energy (DOE) and DOE contractor facilities possessing significant quantities of strategic specialnuclear material (SSNM). Inventory Differences are simply the differences between the amount of material shown in the accounting records and the amount of material reported in the physical inventory. These differences are generally due to errors in estimating material in unmeasurable form at the time of an inventory, unmeasurable holdup in equipment, measurement imprecisions, inaccuracies in initial determinations of SSNM produced or used in nuclear reactors, and inventory or bookkeeping errors. Both DOE and contractors operating DOE facilities carefully maintain, analyze, and investigate ID data. Inventory Differences are expected in nuclear material processing and are not, in and of themselves, evidence of lost or stolen material. On the other hand, ID analysis provides valuable information on the effectiveness of the safeguards system's physical protection and material control measures as well as a check on the process controls and material management procedures. ID's outside safeguards control limits or involving a missing SSNM discrete item are investigated. If necessary, an operation may be shut down until an ID is resolved

There are some special problems in setting up nuclear medicine in a developing country. They can be briefly described in the form of the following general rules. 1) Impossible triangle. For the practice of nuclear medicine, three things are needed: Instrument, Radiopharmaceutical and a Patient. In a developing country, these three become three sides of an impossible triangle. When the radiopharmaceutical is available, the instrument may not be working; when the instrument is functioning, the radiopharmaceutical may not have been obtained from the foreign supplier; and when both are there, the patient might no longer be in the hospital. Three sides of this triangle never join to become a congruent whole. 2) Reverse square law. Further away one is from the source of supply of instruments and radiopharmaceuticals, the problems multiply by the square of this distance. 3) Future of nuclear medicine is tied to the electrical supply available in a developing country. These problems related to power supply are described in the Chapter on maintenance of instruments

This specification presents the requirements for cylindrical metal-sheathed, electrical resistance heaters with compacted mineral-oxide insulation for nuclear or other specialized service. The intended use of a sheathed heater in a specific nuclear or general application will require an evaluation by the purchaser of the compatibility of the heater assembly in the proposed application including the effects of the integrated proposed application including the effects of the integrated neutron flux, temperature, and atmosphere on the properties of the materials of construction. This specification does not include all possible specifications, standards, etc. for materials that may be used in sheathing, insulation, resistance wire, or conductors wire in nuclear environments. The requirements of this specification include only the austenitic stainless steels and nickel-based alloys for sheathing; magnesium oxide, aluminum oxide, beryllium oxide for insulation; and nickel-chromium or iron-chromium-aluminum heater elements with or without low-resistance connecting wires. The intent of this specification is to present the requirements for heaters capable of operating at sheath temperatures and heat fluxes that will limit the maximum internal heater-element temperature to 1050 0 C

Thomas Schelling's ideas to assess the regional strategic framework, and finds systemic uncertainties which suggest that escalation by various parties - state and non-state actors - is a possible outcome. Both near-term and long-term scenarios are considered. The near-term nuclear use scenarios are all predicated on the assumption that nuclear use will occur within the context of escalation to or within war. As dangerous as these circumstances are, longer-term scenarios for nuclear use will also be proposed, which, like the alarming near-term scenarios, flow from the same unstable regional dynamics. The Middle East's unstable dynamics occur within a global environment characterized by a general sense of insecurity about various nuclear issues. Reflecting this situation, the Bulletin of Atomic Scientists recently moved its 'Doomsday Clock' from seven- to five minutes to midnight - the most advanced setting since 1981. Citing Iran's nuclear ambitions, North Korea's test of a nuclear weapon, the failure to secure nuclear materials, a controversial U.S. nuclear doctrine that some argue suggests an expanded role for nuclear weapons, and the continued presence of 26,000 nuclear weapons in the United States and Russia, the Bulletin expressed new concerns about global strategic stability. These developments occurred against a backdrop of the collapse of the 2005 Nonproliferation Treaty Review conference due, among other things, to disinterest in the global community in supporting the spread of nonproliferation norms. (author)

for survival'. The paper first draws upon Thomas Schelling's ideas to assess the regional strategic framework, and finds systemic uncertainties which suggest that escalation by various parties - state and non-state actors - is a possible outcome. Both near-term and long-term scenarios are considered. The near-term nuclear use scenarios are all predicated on the assumption that nuclear use will occur within the context of escalation to or within war. As dangerous as these circumstances are, longer-term scenarios for nuclear use will also be proposed, which, like the alarming near-term scenarios, flow from the same unstable regional dynamics. The Middle East's unstable dynamics occur within a global environment characterized by a general sense of insecurity about various nuclear issues. Reflecting this situation, the Bulletin of Atomic Scientists recently moved its 'Doomsday Clock' from seven- to five minutes to midnight - the most advanced setting since 1981. Citing Iran's nuclear ambitions, North Korea's test of a nuclear weapon, the failure to secure nuclear materials, a controversial U.S. nuclear doctrine that some argue suggests an expanded role for nuclear weapons, and the continued presence of 26,000 nuclear weapons in the United States and Russia, the Bulletin expressed new concerns about global strategic stability. These developments occurred against a backdrop of the collapse of the 2005 Nonproliferation Treaty Review conference due, among other things, to disinterest in the global community in supporting the spread of nonproliferation norms. (author)

The volume discuss nuclear structure of light and nuclei far from stability. The discussions took place in five sessions. In session 1 β decay, in session 2 nuclei near N=20, in session 3 radioactive ion beams' study with help of electromagnetic separators, in session 4 beta decay of light nuclei, in session 5 further papers were discussed in shell models, binding energy and chart of nuclides. (G.P.)

The International Geomechanical Commission is an independent group of experts in rock mechanics and hydrology. This commission has carried out a study on the rocks stability and hydrology of the atolls of Mururoa and Fangataufa (French Polynesia) after the stoppage of the French underground nuclear tests (147 tests all of all, from which 6 took place in 1995 and 1996). This book presents the results of this study. (J.S.)

The stabilities of high-level nuclear waste forms in a repository environment are briefly discussed. The advantages and disadvantages of such waste forms as borosilicate glass, supercalcine ceramics, and synthetic minerals are presented in context with the different rock types which have been proposed as possible host rocks for repositories. It is concluded that the growing geochemical evidence favors the use of a silicate rock repository because of the effectiveness of aluminosilicate rocks as chemical barriers for most radionuclides

India has designed its three-stage nuclear power program based on domestic limited resources of uranium and vast availability of thorium, where natural and enriched uranium-dioxide fuel is utilized in Pressurized Heavy Water Reactors (PHWR) and Boiling Water Reactors (BWR) respectively in the first stage. Plutonium based fuels are implemented for Fast Breeder Reactors (FBR) in the second stage and thorium based fuels are to be utilized using indigenously developed reactors in the third stage. Considering the harsh reactor operating conditions like high temperature and pressure and neutron flux, in-core components used in the above reactors are to be manufactured with different critical materials like Zirconium alloys, Special SS materials, ODS etc. Welding the best joining technique used for joining in-core components, and can perform satisfactorily in the reactors. The welding processes used in nuclear applications have to conform to stringent quality requirements to achieve zero failures rate. In view of the stringent weld quality requirements and amenable for automation various weld joint designs and welding processes were selected for fabrication of in-core components such as Resistance Welding, Tungsten Inert Gas welding and Electron Beam Welding. In this paper, overview is given for all the major welding processes used and its specific applications for fabrication of in-core components used in nuclear reactors. The welding process intricacies are explained and weld quality evaluation techniques are briefly brought out. The joint design modifications and improvements achieved with respect to welding operations over decades of reactor operating experiences are also explained, which helped in reducing fuel and in-core structural components failures for Indian nuclear reactors. (author)

Far from stability, the nuclear structure that is predicted by the shell model is evolving. Old magic numbers disappear, while new ones appear. Our understanding of the underlying nuclear force that drives these changes is still incomplete. After a short overview across the nuclear chart, we discuss the strength functions of the shell-model orbitals in the neutron-rich copper isotopes towards the 78 Ni doubly-magic nucleus. These were measured in a 72 Zn(d, 3 He) 71 Cu proton pick-up reaction in inverse kinematics with a radioactive beam at the Ganil laboratory in France. We also present the latest results from a 80 Zn(p,2p) 79 Cu knockout experiment at Riken in Japan, leading to selective population of hole states in 79 Cu. Our findings show that the Z=28 shell gap in the neutron-rich copper isotopes is surprisingly steady against the addition of neutrons beyond N=40. (author)

This report contains a preliminary evaluation of potential fill materials that could be used to fill void spaces in and around used nuclear fuel contained in dry storage canisters in order to stabilize the geometry and mechanical structure of the used nuclear fuel during extended storage and transportation after extended storage. Previous work is summarized, conceptual descriptions of how canisters might be filled were developed, and requirements for potential fill materials were developed. Elements of the requirements included criticality avoidance, heat transfer or thermodynamic properties, homogeneity and rheological properties, retrievability, material availability and cost, weight and radiation shielding, and operational considerations. Potential fill materials were grouped into 5 categories and their properties, advantages, disadvantages, and requirements for future testing were discussed. The categories were molten materials, which included molten metals and paraffin; particulates and beads; resins; foams; and grout. Based on this analysis, further development of fill materials to stabilize used nuclear fuel during storage and transportation is not recommended unless options such as showing that the fuel remains intact or canning of used nuclear fuel do not prove to be feasible.

Most studies of the climatic effects of nuclear war have used atmospheric models with simple representations of important physical processes. In this work, a model is used which treats the diurnal cycle of insolation, and includes surface and boundary layer parameterizations which take into account static stability and a four-layer soil model. Three idealized experiments are described in which a band of smoke is prescribed over northern mid-latitudes in In the experiment, the standard model is used, in the second the effect of deep soil layers is ignored and in the third the stability dependence in the surface and boundary layer processes is removed. It is found that the inclusion of deep soil layers decreases the surface cooling by about 20%, whereas the inclusion of stability effects increases the cooling by about the same amount, though conclusions will depend to some extent on the model used. copyright American Geophysical Union 1988

The Argonne National Laboratory and Sandia National Laboratory have recently installed an activated barrier, the Access Denial System (ADS) for the upgrade of safeguards of specialnuclear materials. The technology of this system was developed in the late 70's by Sandia National Laboratory-Albuquerque. The installation was the first for the Department of Energy. Subsequently, two additional installations have been completed. The Access Denial System, combined with physical restraints, provide the system delay. The principal advantages of the activated barrier are: (1) it provides an order of magnitude improvement in delay over that of a fixed barrier, (2) it can be added to existing vital areas with a minimum of renovations, (3) existing operations are minimally impacted, and (4) health and safety risks are virtually nonexistent. Hardening of the vital areas using the ADS was accomplished in a cost-effective manner. 3 references, 1 figure, 1 table

A preliminary examination is reported of several special ways for space disposal of nuclear waste material which utilize the radioactive heat in the waste to assist in the propulsion for deep space trajectories. These include use of the wastes in a thermoelectric generator (RTG) which operates an electric propulsion device and a radioisotope - thermal thruster which uses hydrogen or ammonia as the propellant. These propulsive devices are compared to the space tug and the space tug/solar electric propulsion combination for disposal of waste on a solar system escape trajectory. Such comparisons indicate that the waste-RTG approach has considerable potential provided the combined specific mass of the waste container - RTG system does not exceed approximately 150 kg/kw sub e. Several exploratory numerical calculations have been made for high earth orbit and Earth escape destinations.

Full Text Available Characterization of specialnuclear material may be performed using energy spectroscopy of either the neutron or gamma-ray emissions from the sample. Gamma-ray spectroscopy can be performed relatively easily using high-resolution semiconductors such as high-purity germanium. Neutron spectroscopy, by contrast, is a complex inverse problem. Here, results are presented for 252Cf and PuBe energy spectra unfolded using a single EJ309 organic scintillator; excellent agreement is observed with the reference spectra. Neutron energy spectroscopy is also possible using a two-plane detector array, whereby time-of-flight kinematics can be used. With this system, energy spectra can also be obtained as a function of position. Spatial-dependent energy spectra are presented for neutron and gamma-ray sources that are in excellent agreement with expectations.

The system of examinations of selected staff members of Czechoslovak nuclear power plants for their special professional quanlification is described in detail. This selected personnel includes secondary circuit operators, primary circuit operators, graduate shift leaders as well as reactor unit managers. Attention is paid to the structure, methodology, contents and criteria of evaluation of the written, oral and practical parts of the examination, which is sat for before the State Examination Commission. Based on the results of the examinations, the Czechoslovak Atomic Energy Commission grants, prolongs or cancels licenses for the particular functions. Over the period from 1985 to March 1989, 394 new licenses were issued, 93 licenses were prolonged and 4 were withdrawn. (Z.M.). 7 figs., 3 tabs., 3 refs

This guide describes the type of information needed to evaluate an application for a specific license for receipt, possession, use, and transfer of specialnuclear material. It is intended for applicants requesting authorization to possess and use up to 2000 grams of plutonium, total, in the form of sealed plutonium-beryllium neutron sources, and any specialnuclear material in quantities and forms not sufficient to form a critical mass. The latter quantities are considered to be 350 grams of contained uranium-235, 200 grams of uranium-233, 200 grams of plutonium (in any form other than plutonium-beryllium neutron sources) or any combination of them

This Environmental Impact Appraisal is issued by the US Nuclear Regulatory Commission in response to an application by GA Technologies, Inc., (GA) for renewal of SpecialNuclear Material (SNM) License No. SNM-696 covering plant operations at San Diego, California. The proposed action provides for continuing research, development, and production activities involving SNM, uranium enriched in the U-235 and U-233 isotopes, and plutonium

Full Text Available Stability of the stationary wave of nuclear burning in fast reactor with uranium-plutonium fuel chain is inves-tigated. The reactor model including 1-D diffusion equation in one-group approximation for neutron flux density and kinetic equations for nuclear densities describes slow evolution of nuclear densities followed by neutron flux. New analytical approach was proposed, which is based on the approximation of small wave velocity of the stationary wave. We obtain so-called wave velocity characteristic of the reactor which is the dependence of wave velocity to the effective absorber concentration. We show that due to instability of long-living 241Pu a turning point and lower branch of stationary solutions appear. Numerical solution of the time dependent problem proves that the solutions of the lower branch are unstable. Thus, the turning point of the velocity characteristic corre-sponds to the lower margin of possible wave velocities of nuclear fission waves of the steady shape. At the same time the solutions of the upper branch are stable with respect to slow evolution of nuclear densities.

The Phenomena Identification and Ranking Table (PIRT) technique was conducted on the Special Purpose Reactor nuclear plant design. The PIRT is a structured process to identify safety-relevant/safety-significant phenomena and assess the importance and knowledge base by ranking the phenomena. The Special Purpose Reactor is currently in the conceptual design stage. The candidate reactor has a solid monolithic stainless steel core with an array of heat pipes and fuel pellets embedded in the monolith. The heat pipes are used to remove heat from the core using simple, reliable, and well-characterized physics (capillarity, boiling, and condensation). In the initial design, one heat exchanger is used for the working fluid that produces energy, and a second heat exchanger is used to remove decay heat in emergency or shutdown conditions. In addition, a power conversion cycle such as an open-air Brayton system is available as an option for power conversion and process heat. This report summarizes and documents the process and scope of the four PIRT reviews, noting the major activities and conclusions. The identified phenomena, analyses, rationales, and associated ratings are presented along with a summary of the findings from the four individual PIRTs, namely (1) Reactor Accident and Normal Operations, (2) Heat Pipes, (3) Materials, and (4) Power Conversion. The PIRT reports for these four major system areas evaluated are attached as appendixes to this report and provide considerably more detail about each assessment as well as a more complete listing of the phenomena that were evaluated.

The President of the Deutsches Atomforum, Dr. Walter Hohlefelder, emphasized in his opening address at the 2008 Annual Nuclear Technology Conference in Hamburg that the German special approach to nuclear power utilization led straight into a dead end of energy policy. ''The outcome is foreseeable: The ambitious German goals of carbon dioxide reduction are missed, the competitiveness of the country is jeopardized, dependency on foreign energy imports rises,'' Dr. Hohlefelder stated. In view of the growing challenges in energy policy Germany had no alternative but to reassess nuclear power. The only outcome of this reappraisal could be extension of the life of nuclear power plants currently in operation. This was necessary also in order to avoid an impending gap in German electricity supply, Dr. Hohlefelder added. He invited all stakeholders to join in an open, unbiased dialog. Dr. Hohlefelder openly criticized the continued ban on research into the development of new reactors. ''A policy of this kind, a policy which bans thinking, is unacceptable in a technology-oriented, industrialized nation such as Germany.'' Nuclear power technology as a high-tech area was a unique achievement which had contributed to the prosperity of the country. The Annual Nuclear Technology Conference, which was held for the 39th time this year, is one of the biggest specialized conferences in the nuclear field with an attendance, this year, of approximately 1300 participants from more than twenty nations. (orig.)

This report summarizes the feasibility and the effectiveness of using stabilizers (internal metal structural components) to augment the heat transfer characteristics of a nuclear waste canister. The problem was modeled as a transient two-dimensional heat transfer in two physical domains - the stabilizer and the wedge (a 30-degree-angle canister segment), which includes the heat-producing spent-fuel rods. This problem is solved by a simultaneous and interrelated numerical investigation of the two domains in cartesian and polar coordinate systems. The numerical investigations were performed for three cases. In the first case, conduction was assumed to be the dominant mechanism for heat transfer. The second case assumed that radiation was the dominant mechanism, and in the third case both radiation and conduction were considered as mechanisms of heat transfer. The results show that for typical conditions in a waste package design, the stabilizers are quite effective in reducing the overall temperature in a waste canister. Furthermore, the results show that increasing the stabilizer thickness over the thickness specified in the present design has a negligible effect on the temperature distribution in the canister. Finally, the presence of the stabilizers was found to shift the location of the peak temperature areas in the waste canister

A delayed neutron counting (DNC) system, where the sample to be analyzed remains stationary in a thermal neutron beam outside of the reactor, has been developed at the National Research Universal (NRU) reactor of the Canadian Nuclear Laboratories (CNL) at Chalk River. The new in-beam DNC is a novel approach for non-destructive characterization of specialnuclear materials (SNM) that could enable identification and quantification of fissile isotopes within a large and shielded sample. Despite the orders of magnitude reduction in neutron flux, the in-beam DNC method can be as informative as the conventional in-core DNC for most cases while offering practical advantages and mitigated risk when dealing with large radioactive samples of unknown origin. This paper addresses (1) the qualification of in-beam DNC using a monochromatic thermal neutron beam in conjunction with a proven counting apparatus designed originally for in-core DNC, and (2) application of in-beam DNC to an examination of large sealed capsules containing unknown radioactive materials. Initial results showed that the in-beam DNC setup permits non-destructive analysis of bulky and gamma shielded samples. The method does not lend itself to trace analysis, and at best could only reveal the presence of a few milligrams of 235U via the assay of in-beam DNC total counts. Through analysis of DNC count rates, the technique could be used in combination with other neutron or gamma techniques to quantify isotopes present within samples.

A Special safety report of the Slovak Republic in 2012 is presented. An account of activities carried out by the Nuclear Regulatory Authority of the Slovak Republic (UJD) is presented. These activities are reported under the headings: (0) Introduction; (0.1) Purpose of the report; (0.2) Brief description of the site characteristics and units; (1) Executive summary; (2) External events; (2.1) Seismic; (2.2) Flooding; (2.3) Extreme weather conditions; (3) Design issues; (3.1) Loss of electrical power; (3.2) Loss of the decay heat removal capability/ultimate heat sink; (3.3) Loss of the primary ultimate heat sink, combined with station black out (see stress tests specifications); (4) Severe accident management; (4.1) Organization and arrangements of the licensee to manage accidents; (4.2) Accident management measures in place at the various stages of a scenario of loss of the core cooling function; (4.3) Maintaining the containment integrity after occurrence of significant fuel damage (up to core meltdown) in the reactor core; (4.4) Accident management measures to restrict the radioactive releases; (5) National organizations (regulator, technical support organizations, operator, government); (5.1) Legislative and regulatory framework; (6) Emergency preparedness and response and post--accident management (off-site); (6.1) Implementation of legislation in the field of emergency preparedness; (7) International cooperation; (7.1) Conventions and communications; (7.2) Cooperation with the international organizations; (7.3) Providing feedback including occurrences at nuclear installations of other nuclear power plants abroad.

In a September 1993 address to the United Nations General Assembly, President Clinton announced a new nonproliferation and export control policy that established a framework for US efforts to prevent the proliferation of weapons of mass destruction. The new policy proposed that the US undertake a comprehensive approach to the growing accumulation of fissile material. One of the key elements was for the US to support a specialnuclear materials (SNM) multilateral convention prohibiting the production of highly enriched uranium (HEU) or plutonium for nuclear explosives purposes or outside of international safeguards. This policy is often referred to as the President's Cutoff Initiative or the Fissile Material Cutoff Treaty (FMCT). Because both the US Department of Energy (DOE) and foreign reprocessing facilities similar to PUREX will likely to be inspected under a FMCT, the DOE Office of Arms Control and Nonproliferation, Negotiations and Analysis Division (DOE/NN-41) tasked Pacific Northwest Laboratory (PNL) to perform an information gathering exercise, the PUREX Exercise, using the Plutonium-Uranium Extraction (PUREX) Plant located on the Hanford Site in Washington State. PUREX is a former production reactor fuel reprocessing plant currently undergoing a transition to a ''decontamination and decommissioning (D ampersand D) ready'' mode. The PUREX Exercise was conducted March 29--30, 1994, to examine aspects of the imposition of several possible cutoff regimes and to study verification of non-production of SNM for nuclear weapons purposes or outside of safeguards. A follow-up activity to further examine various additional verification regimes was held at Los Alamos National Laboratory (LANL) on May 10, 1994

A fuzzy logic controller(FLC) and a fuzzy logic filter(FLF), which have a special type of fuzzifier, inference engine, and defuzzifier, are applied to the water level control of a nuclear steam generator (S/G). It is shown that arbitrary two-input, single-output linear state feedback controllers can be adequately expressed by this FLC. A procedure to construct stability-guaranteed FLC rules is proposed. It contains the following steps: (1) The stable sector of linear feedback gains is obtained from the suboptimal concept based on LQR theory and the Lyapunov's stability criteria: (2) The stable sector of linear gains is mapped into two linear rule tables that are used as limits for the FLC rules: (3) The construction of an FLC rule table is done by choosing certain rules that lie between these limits. This type of FLC guarantees asymptotic stability of the control system. The FLF generates a feedforward signal of S/G feedwater from the steam flow measurement using a fuzzy concept. Through computer simulation, it is found that the FLC with the FLF works better than well-tuned PID controller with variable gains to reduce swell/shrink phenomena especially for the water level deviation and abrupt steam flow disturbances that are typical in the existing power plants. A neurofuzzy logic controller (NFLC), that is implemented by using multi-layered neural network to have the same function as the FLC discussed above, is designed. The automatic generation of NFLC rule table is accomplished by using back-error-propagation (BEP) algorithm. There are two separated paths at the error back-propagation in the S/G. One is to consider the level dynamics depending on the tank capacity, and the other is to take into account the reverse dynamics of S/G. The amounts of error back-propagated through these paths show opposite effects to the BEP algorithm each other at the swell/shrink phenomena. Through the computer simulation, it is found that the BEP algorithm adequately generates NFLC

The first part of this research thesis on the stability of organic ligands in radioactive environment, reports the study of the stability of the dicyclohexano-18-crown-6 (DCH18C6) in radioactive environment by using several analytical techniques (nuclear magnetic resonance or NMR, X-ray diffraction, Fourier transform infrared spectroscopy or FTIR, gas chromatography or GC, and coupled gas chromatography/mass spectroscopy). The seven main radiolysis products of DCH18C6 are identified and then synthesised to be tested in radioactive environment. These products are soluble in nitric medium, and partially precipitate plutonium, but cannot in any case disturb the reprocessing process based on a continuous extraction system. Chemical yields are computed and DCH18C6 appears to be a serious candidate for the reprocessing of spent nuclear fuels. The second part reports the study of the stability of the poly(4-vinylpyridine) or P4VP in radioactive environment. It appears that gamma radiations produce radicals in the P4VP which recombine in function of the irradiation dose. However, this material is very stable in acid environment and radioactive environment [fr

A study was made of the stability of the high temperature gas-cooled pebble bed core against xenon-driven oscillation. This generic study indicated that a core as large as 3000 MW(t) could be stable. Several aspects present a challenge to analysis including the void space above the pebble bed, the effects of possible control rod configurations, and the temperature feedback contribution. Special methods of analysis were developed in this effort. Of considerable utility was the scheme of including an azimuthal buckling loss term in the neturon balance equations admitting direct solution of the first azimuthal harmonic for a core having azimuthal symmetry. This technique allows the linear stability analysis to be done solving two-dimensional (RZ) problems instead of three-dimensional problems. A scheme for removing the fundamental source contribution was also implemented to allow direct iteration toward the dominant harmonic solution, treating up to three dimensions with diffusion theory

For decades, the Asian security environment has been characterized by multiple strategic rivalries with cascading effects. Due to its competition with China, India modernizes its armed forces, thus reinforcing its conventional advantage over Pakistan. In the subcontinent, geography, military imbalance, the legacy of past conflicts and infiltration of extremist groups considerably weaken strategic stability. To strengthen its deterrent capability against its stronger neighbour, Pakistan faces significant challenges in developing a conventional response to perceived threats from India. Islamabad thus committed to a 'full spectrum' build-up of its nuclear forces, which includes the development of tactical nuclear weapons. As Cold War experience informs, far from simply strengthening its deterrent vis-a-vis India, this move poses numerous operational dilemmas for Pakistan. The ongoing regional quantitative and qualitative arms race combines with continued political tensions between India and Pakistan to create a worrying strategic dynamic in South Asia. (author)

The LPAD (French Atomic Energy Commission) develops innovative processes in the frame of the future dismantling of nuclear facilities. Formulations were developed using high viscosified foams stabilized by biodegradable nonionic surfactants: alkyl poly-glucosides and viscosifiers (xanthan gum), which allow us to increase the foam lifetime and thus contact time of chemical reactants with the facility walls. We have considered the relationships between physicochemical properties and foam stability through the exploration of the foam at three different scales: from the molecular range (micelles, surface tension and visco-elasticity), to the film and Plateau border range (XR reflectivity, surface shear viscosity) and to macroscopic range, meaning the whole foam (foaminess, liquid fraction and wall film thickness evolution). Finally, exploratory study is presented concerning simultaneous foam three scales characterisation by small angle neutron scattering. (author)

A simple mathematical model is developed to describe the dynamics of the nuclear-coupled thermal-hydraulics in a boiling water reactor (BWR) core. The model, which incorporates the essential features of neutron kinetics, and single-phase and two-phase thermal-hydraulics, leads to simple dynamical system comprised of a set of nonlinear ordinary differential equations (ODEs). The stability boundary is determined and plotted in the inlet-subcooling-number (enthalpy)/external-reactivity operating parameter plane. The eigenvalues of the Jacobian matrix of the dynamical system also are calculated at various steady-states (fixed points); the results are consistent with those of the direct stability analysis and indicate that a Hopf bifurcation occurs as the stability boundary in the operating parameter plane is crossed. Numerical simulations of the time-dependent, nonlinear ODEs are carried out for selected points in the operating parameter plane to obtain the actual damped and growing oscillations in the neutron number density, the channel inlet flow velocity, and the other phase variables. These indicate that the Hopf bifurcation is subcritical, hence, density wave oscillations with growing amplitude could result from a finite perturbation of the system even where the steady-state is stable. The power-flow map, frequently used by reactor operators during start-up and shut-down operation of a BWR, is mapped to the inlet-subcooling-number/neutron-density (operating-parameter/phase-variable) plane, and then related to the stability boundaries for different fixed inlet velocities corresponding to selected points on the flow-control line. The stability boundaries for different fixed inlet subcooling numbers corresponding to those selected points, are plotted in the neutron-density/inlet-velocity phase variable plane and then the points on the flow-control line are related to their respective stability boundaries in this plane.

The cause of an intermittent load loss at Oldbury Nuclear Power Station is shown to be the high sensitivity of boiler performance to the imposed spatial distribution of boiler gas inlet temperature. This high sensitivity is demonstrated to be a function of the inherent static stability characteristics of the boilers. The installation of orifice plates with a high flow resistance into the feed pipework to the half boilers has greatly reduced the boiler sensitivity and eliminated the intermittent load loss so that, on average, higher electrical generation is obtained from the station. (author)

In the last few years, our understanding of nuclei at extremes of stability has undergone substantial development and change. It is now thought that there is every likelihood for truly new manifestations of structure at extreme N/Z ratios, unlike anything observed to date. Changes in shell structure, residual interactions, symmetries, collective modes, and the evolution of structure are envisioned. These developing ideas expand the opportunities for nuclear structure studies with radioactive beams and focus attention on the need to develop efficient experimental techniques and improved signatures of structure. These developments are discussed along with an overview of current and future radioactive beam projects in North America

The viability of using Bubble Chambers as dark matter particle detectors is considered. Techniques leading to the enhanced chamber stability needed for this new application are described in detail. Prototype trials show that sensitivity to the low-energy nuclear recoils induced by Weakly Interacting Massive Particles (WIMP) is possible in conditions of extreme insensitivity to minimum ionizing backgrounds. An understanding of detector response is demonstrated using existing theoretical models. We briefly comment on the prospects for detection of supersymmetric dark matter with large CF 3 I chambers

The effects of a nuclear electromagnetic pulse (EMP) on the synchronous stability of the electric power transmission and distribution systems are evaluated. The various modes of coupling of EMP to the power system are briefly discussed, with particular emphasis on those perturbations affecting the synchronous stability of the transmission system. A brief review of the fundamental concepts of the stability problem is given, with a discussion of the general characteristics of transient analysis. A model is developed to represent single sets as well as repetitive sets of multiple faults on the distribution systems, as might be produced by EMP. The results of many numerical stability calculations are presented to illustrate the transmission system's response from different types of perturbations. The important parameters of both multiple and repetitive faults are studied, including the dependence of the response on the size of the perturbed area, the fault density, and the effective impedance between the fault location and the transmission system. Both major load reduction and the effect of the opening of tie lines at the time of perturbation are also studied. We conclude that there is a high probability that EMP can induce perturbations on the distribution networks causing a large portion of the transmission network in the perturbed area to lose synchronism. The result would be an immediate and massive power failure

This paper shows how Fluor Hanford and BNG America have combined nuclear plant skills from the U.S. and the U.K. to devise methods to retrieve and treat the sludge that has accumulated in K Basins at the Hanford Site over many years. Retrieving the sludge is the final stage in removing fuel and sludge from the basins to allow them to be decontaminated and decommissioned, so as to remove the threat of contamination of the Columbia River. A description is given of sludge retrieval using vacuum lances and specially developed nozzles and pumps into Consolidation Containers within the basins. The special attention that had to be paid to the heat generation and potential criticality issues with the irradiated uranium-containing sludge is described. The processes developed to re-mobilize the sludge from the Consolidation Containers and pump it through flexible and transportable hose-in-hose piping to the treatment facility are explained with particular note made of dealing with the abrasive nature of the sludge. The treatment facility, housed in an existing Hanford building, is described, and the uranium-corrosion and grout packaging processes explained. The uranium corrosion process is a robust, tempered process very suitable for dealing with a range of differing sludge compositions. Optimization and simplification of the original sludge corrosion process design is described and the use of transportable and reusable equipment is indicated. The processes and techniques described in the paper are shown to have wide applicability to nuclear cleanup.

... is calculated in accordance with § 170.285(a); and (2) The slack surface in the roll stabilization... in the roll tank on Graph 170.295. (3) Construct a line A on Graph 170.295 so that the area under line A between T = 0 and the angle at which the deck edge is immersed or 28 degrees, whichever is...

The new draft DOE Material Control and Accountability Order 5633.3 requires that facilities handling specialnuclear material (SNM) evaluate their effectiveness against provided theft of SNMProtracted theft means repeated thefts of small quantities of material to accumulate a goal quanfity. To evaluate the safeguards effectiveness against pro thefts, one must addresses several issues: (1) defining relevant time frames for various threat scenarios and delayed detection safeguards: (2) identifying which safeguards come into play more than once because of repeated adversary actions or because of periodic occurrence during the theft time frame (e.g., daily administrative check on presence of material): (3) considering whether the second and subsequent applications of safeguards are different in effectiveness from the first; (4)synthesizing how physical security, material control, and material accountability safeguards combine to provide protection against protracted theft scenarios. In this paper we discuss these issues and describe how we are augmenting the Analytic System and Software for Evaluating Safeguards and Security (ASSESS) to provide the user with a tool for evaluating effectiveness against protracted theft. Currently, the Insider module of ASSESS focuses on evaluating the ''timely'' detection of abrupt theft attempts by various types of single nonviolent insiders. In this paper we describe the approach we're implementing to augment ASSESS to handle various cases of protracted theft attempts

Results are presented of technical and economical analysis of advisability of constructing combined Nuclear Power and Heating Plants (NPHP) assuring the possibility of their location near the areas of heat power consumption in case of observing a given degree of radiation safety for population and personnel. Specific features determining the choice of turbine-driven units for such plants are analyzed. Conditions of competiveness of a specialized NPHP with alternative power units, NPHP based on the WWER-1000 reactor and district heating plants (NDHP), are determined. Analysis of design specifications of NPHP with two VK-500 reactor units and structures of capital investments in such a plant reveal that an increase in the total capital investments in the NPHP would not exceed 2% with account of the difference in costs for grid heaters and a corresponding change in dimensions of operation rooms as well as changes in costs of heat removal system (within one site) at the TK turbine replacement by the T turbine

The USNRC requires each licensee who is authorized to possess SpecialNuclear Materials (SNM) to prepare and submit reports concerning SNM received, produced, possessed, transferred, consumed, disposed of, or lost. These SNM accountability reports, which need to be submitted twice a year, contain detailed information on the origin, quantity, and type of SNM for several locations. The amount of detail required makes these reports very time consuming and error prone when prepared manually. Yankee Atomic is developing an IBM PC-based computer code that fully automates the process of generating SNM accountability reports. The program, called SNMSP II, prints a number of summaries including facsimiles of the NRC/DOE-741, 742, 742C, and RW-859 reports in a format that can be submitted directly to the NRC/DOE. SNMSP II is menu-driven and is especially designed for people with little or no computer training. Input can be either from a mainframe-based corporate data base or manually through user-friendly screens. In addition, extensive quality assurance features are available to ensure the security and accuracy of the data. This paper discusses the major features of the code and describes its implementation at Yankee

AND DATES COVERED Capstone project report 4. TITLE AND SUBTITLE STABILIZATION OPERATIONS THROUGH MILITARY CAPACITY BUILDING— INTEGRATION BETWEEN...in Chapter VI. According to the 2013 report Denmark’s Integrated Stabilisation Engagement in Fragile and Conflict-Affected Areas of the World...assembled task force would be able to be considered fully integrated , and might not integrate fully before the mission. One disadvantage to “coding

Working robots are used for the reduction of radiation exposure in the radiation domains such as the underwater operation in a periodic inspection of nuclear power plants and reprocessing facilities. In addition, there are many cases that a multiple joint robot is adopted to raise versatility of the work in the special environment. In future, adopting it in the scene of the accident including the Fukushima-Daiiti nuclear power plant of Tokyo Electric Power Company, is also expected. Therefore, it is necessary to improve operability for remote control of multiple joint robots. In this paper, we propose it by using 3D simulator. (author)

The topics presented in this newsletter are: IAEA's Contribution to Peaceful Use of Nuclear Power by Mr. Sinha; IAEA's Contribution to Peaceful Use of Nuclear Power by Mr. Tipping; Message from the Director of the Division of Nuclear Power; Nuclear power plant operating performance and life cycle management; Improving organizational performance; Coordination of INPRO; Technology development for advanced reactors; Support for non-electric applications of nuclear power; Planned meetings in 2006 and 2007; Division of Nuclear Power Web site link. The first two topics have been indexed separately

The development of special conducting plastics to meet the special needs of radiation dosimetry is reported. The most critical application of the special plastics is in the construction of ionization chambers which provide the best means of accurately measuring absorbed dose and exposure, low-noise signal cables, and electrometers for the ionization chambers are described

The attributions of Brazilian CNEN in the licensing procedures of any nuclear installation are discussed. It is shown that the work safety engineering and industrial safety constitute important functions for nuclear safety. (M.C.K.) [pt

The focus of this study is the development and understanding of polymer based burnable poison rod assemblies (BPRAs) in pressurized water reactors (PWRs). This material substitution reduces the water displacement penalty at the end of cycle (EOC) currently found with the B4C/Al 2O3 BPRAs that displace moderator water in PWRs. This gives rise to a longer fuel cycle due to the extra moderation from hydrogen in polymer structures. Finding synthetic polymers that endure a severe nuclear reactor circumstance is a challenge. Aside from the proper thermal stability at the range of 350--600°C in the core for a single cycle, the hydrothermal stability at near-critical water condition (350°C, 20.7MPa) is required to maintain the safe and controlled nuclear reaction because a danger comes if water might possibly penetrate inside the burnable poison rod by the failure of zircaloy cladding. There are two approaches to obtain a boron source (burnable position material) in hydrogen containing polymers. One is to utilize the boron source directly by synthesizing boron-containing polymers. A second approach is to find commercial polymers that have an appropriate thermal, hydrothermal, radiational stability and high hydrogen content; and then add an inorganic boron source such as B4C to form a composite material. Poly (diacetylene-siloxane-carborane)s and other silicon based precursor polymers were introduced to observe their thermal and hydrothermal stability. However, we found that the degradation of Si-O-Si, which was presented in the polymer, was an unfavorable disadvantage under near-critical water (350°C, 20.7MPa) even though they formed dense network structures. In addition, the Si-O bond is quite sensitive to variety of reagents, including base and acid. Therefore, the degradation rate might be accelerated by high H+ and OH- ion concentrations at the near-critical water condition. For the second approach, a number of candidate matrix polymers were screened for new

Since 1947 DOE and its predecessor agencies, AEC and ERDA, have moved nuclear materials by a variety of commercial and government transportation modes. In the late 1960's world-wide terrorism and other dissident activities prompted the then-AEC to review its procedures for safeguarding SNM. These reviews resulted in immediate and long-range programs for improvement of overall safeguards. Domestic transportation of completed nuclear weapons and SNM used in the weapons program was selected for special consideration. In the early 1970's AEC started the development of a Safe Secure Trailer (SST) to transport nuclear weapons and nuclear components and the development and installation of a high frequency (HF) communications system to assure continuous radio contact between selected highway and rail shipments and Headquarters, Albuquerque Operations (ALO). Late 1974 AEC directed ALO to develop a transportation system to extend weapons-level protection to all AEC SQ SNM shipments and to consolidate, manage, and operate this system. As of September 1976 all SQ SNM was being transported in the Safe Secure DOE (then ERDA) transportation safeguards system, composed of the following principal elements: (1) Transport equipment consisting of Safe Secure Trailers and specially modified towing tractors; Safe Secure Railcars and specially modified escort coaches; and specially designed highway escort vehicles. (2) An automated high-frequency digital radio system that enables continuous communications between the transporting equipment and central control. (3) A courier force that operates all transport equipment (except aircraft and rail power units) and mobile communications equipment; provides armed protection for shipments; and assures proper safety en route. (4) A central Headquarters staff that plans, executes, and controls shipments and directs, manages, and operates the system

The frequency of nuclear aberrations and neutral red retention time of hemocytes in the mollusk Lamellidens marginalis were recorded under exposure to sublethal concentrations of sodium arsenite in order to examine the sensitivity and effectiveness of these inexpensive assays for screening the toxicity of As{sup 3+}in a freshwater ecosystem. A dose and time dependent increase in the density of micronucleated and binucleated hemocytes and gill cells was indicative of the pronounced genotoxic effect of arsenic on this animal. The disruption of intrahemocyte homeostasis imposed by this natural toxicant was evident from a dose and time dependent reduction in the lysosomal stability of the hemocytes of the animal. The tested parameters are indicative of arsenic toxicity in L. marginalis in the freshwater systems of the arsenic affected geographical areas of West Bengal, India. (Abstract Copyright [2009], Wiley Periodicals, Inc.)

According to present plans, high level nuclear waste in Finland is going to be disposed of in bedrock at a depth of several hundred metres. The spent fuel containers will be placed in boreholes drilled in the floors of deposition tunnels with engineered clay buffer, which is made of bentonite blocks. The tunnels will be filled with a mixture of bentonite and crushed rock. For stability calculations a thermomechanical model for compressed bentonite is needed. In the study a thermomechanically consistent model for reversible processes for swelling clays is presented. Preliminary calculations were performed and they show that uncertainty in material parameter values causes significantly different results. Therefore, measurements that are consistent with the model are needed

Highlights: ► The nuclear protein Artemis physically interacts with AMPKα2. ► Artemis co-localizes with AMPKα2 in the nucleus. ► Artemis promotes phosphorylation and activation of AMPK. ► The interaction between AMPKα2 and LKB1 is stabilized by Artemis. -- Abstract: AMP-activated protein kinase (AMPK) is a hetero-trimeric Ser/Thr kinase composed of a catalytic α subunit and regulatory β and γ subunits; it functions as an energy sensor that controls cellular energy homeostasis. In response to an increased cellular AMP/ATP ratio, AMPK is activated by phosphorylation at Thr172 in the α-subunit by upstream AMPK kinases (AMPKKs), including tumor suppressor liver kinase B1 (LKB1). To elucidate more precise molecular mechanisms of AMPK activation, we performed yeast two-hybrid screening and isolated the complementary DNA (cDNA) encoding the nuclear protein Artemis/DNA cross-link repair 1C (DCLRE1C) as an AMPKα2-binding protein. Artemis was found to co-immunoprecipitate with AMPKα2, and the co-localization of Artemis with AMPKα2 in the nucleus was confirmed by immunofluorescence staining in U2OS cells. Moreover, over-expression of Artemis enhanced the phosphorylation of AMPKα2 and the AMPK substrate acetyl-CoA carboxylase (ACC). Conversely, RNAi-mediated knockdown of Artemis reduced AMPK and ACC phosphorylation. In addition, Artemis markedly increased the physical association between AMPKα2 and LKB1. Taken together, these results suggest that Artemis functions as a positive regulator of AMPK signaling by stabilizing the LKB1–AMPK complex.

Highlights: Black-Right-Pointing-Pointer The nuclear protein Artemis physically interacts with AMPK{alpha}2. Black-Right-Pointing-Pointer Artemis co-localizes with AMPK{alpha}2 in the nucleus. Black-Right-Pointing-Pointer Artemis promotes phosphorylation and activation of AMPK. Black-Right-Pointing-Pointer The interaction between AMPK{alpha}2 and LKB1 is stabilized by Artemis. -- Abstract: AMP-activated protein kinase (AMPK) is a hetero-trimeric Ser/Thr kinase composed of a catalytic {alpha} subunit and regulatory {beta} and {gamma} subunits; it functions as an energy sensor that controls cellular energy homeostasis. In response to an increased cellular AMP/ATP ratio, AMPK is activated by phosphorylation at Thr172 in the {alpha}-subunit by upstream AMPK kinases (AMPKKs), including tumor suppressor liver kinase B1 (LKB1). To elucidate more precise molecular mechanisms of AMPK activation, we performed yeast two-hybrid screening and isolated the complementary DNA (cDNA) encoding the nuclear protein Artemis/DNA cross-link repair 1C (DCLRE1C) as an AMPK{alpha}2-binding protein. Artemis was found to co-immunoprecipitate with AMPK{alpha}2, and the co-localization of Artemis with AMPK{alpha}2 in the nucleus was confirmed by immunofluorescence staining in U2OS cells. Moreover, over-expression of Artemis enhanced the phosphorylation of AMPK{alpha}2 and the AMPK substrate acetyl-CoA carboxylase (ACC). Conversely, RNAi-mediated knockdown of Artemis reduced AMPK and ACC phosphorylation. In addition, Artemis markedly increased the physical association between AMPK{alpha}2 and LKB1. Taken together, these results suggest that Artemis functions as a positive regulator of AMPK signaling by stabilizing the LKB1-AMPK complex.

In this paper, a spatial information-theoretic model is proposed to locate sensors for detecting source-to-target patterns of specialnuclear material (SNM) smuggling. In order to ship the nuclear materials from a source location with SNM production to a target city, the smugglers must employ global and domestic logistics systems. This paper focuses on locating a limited set of fixed and mobile radiation sensors in a transportation network, with the intent to maximize the expected information gain and minimize the estimation error for the subsequent nuclear material detection stage. A Kalman filtering-based framework is adapted to assist the decision-maker in quantifying the network-wide information gain and SNM flow estimation accuracy.

Full Text Available In this paper, a spatial information-theoretic model is proposed to locate sensors for detecting source-to-target patterns of specialnuclear material (SNM smuggling. In order to ship the nuclear materials from a source location with SNM production to a target city, the smugglers must employ global and domestic logistics systems. This paper focuses on locating a limited set of fixed and mobile radiation sensors in a transportation network, with the intent to maximize the expected information gain and minimize the estimation error for the subsequent nuclear material detection stage. A Kalman filtering-based framework is adapted to assist the decision-maker in quantifying the network-wide information gain and SNM flow estimation accuracy.

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or specialnuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, all focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

Nuclear weapons proliferation is an existing and growing worldwide problem. To help with devising strategies and supporting decisions to interdict the transport of nuclear material, we developed the Pathway Analysis, Threat Response and Interdiction Options Tool (PATRIOT) that provides an analytical approach for evaluating the probability that an adversary smuggling radioactive or specialnuclear material will be detected during transit. We incorporate a global, multi-modal transportation network, explicit representation of designed and serendipitous detection opportunities, and multiple threat devices, material types, and shielding levels. This paper presents the general structure of PATRIOT, and focuses on the theoretical framework used to model the reliabilities of all network components that are used to predict the most likely pathways to the target.

1.1 This guide briefly describes the state-of-the-art of radiation monitors for detecting specialnuclear material (SNM) (see 3.1.11) in order to establish the context in which to write performance standards for the monitors. This guide extracts information from technical documentation to provide information for selecting, calibrating, testing, and operating such radiation monitors when they are used for the control and protection of SNM. This guide offers an unobtrusive means of searching pedestrians, packages, and motor vehicles for concealed SNM as one part of a nuclear material control or security plan for nuclear materials. The radiation monitors can provide an efficient, sensitive, and reliable means of detecting the theft of small quantities of SNM while maintaining a low likelihood of nuisance alarms. 1.2 Dependable operation of SNM radiation monitors rests on selecting appropriate monitors for the task, operating them in a hospitable environment, and conducting an effective program to test, calibrat...

The magnitude of Russian foreign debt, both official bilateral and commercial, compounded by collapse of the Russian economic system, is an obstacle in preventing the Russian Federation from effectively increasing the domestic priority of drawing down its nuclear weapons complex and providing a healthy, competitive environment to its nuclear cities. Debt-for-nature swaps, introduced in the early 1980s, provide debtor nations with a means of converting a portion of foreign debt into local currency, often at steep discounts, to use for purposes such as environmental protection that serve both a domestic and international need. This paper presents the debt-for-nature concept as a model for providing an infusion of funds to further U.S. and international nonproliferation objectives to help stabilize Russian closed city economic conditions through direct work on proliferation problems and remediation of the environment. A specific proposal is presented to demonstrate the utility and efficacy of the dept swap concept through initial collaboration with the city administration of Ozersk. The purpose of the proposal is to facilitate making Ozersk a safe, healthy competitive city, providing useful employment for its scientists and population and converting its superior infrastructure into productive activities

The necessity to enhance energy supplies from nuclear power in the FRG is based on the following facts: Further development of hydro-electric power meets with constraints set by the geographical and hydrological conditions of the country; use of petroleum and natural gas for electricity generation is likewise limited for reasons of general energy policy; brown coal, similar to nuclear power, offers economic advantages but is limited in reserves, and in geographical distribution. Thus a utility company only has a reduced choice when considering construction of a new plant, the option being either coal or nuclear power. This decision is determined by economic considerations. Protection against hazards emanating from the peaceful uses of nuclear energy, is achieved by a complete safeguards system covering all nuclear activities, from licensing and supervision of design and construction to operational supervision. The positive attitude of the German federal government towards nuclear energy does not meet with approval by all political or social groups in this country. Opposition against nuclear energy has been quite successful to a certain extent and has hampered the further development of nuclear power up to now. Acceptance of nuclear energy among the population has risen again to currently about 60%, after a slump following the Harrisburg event. Opponents to nuclear energy account for about 12% of the population, as revealed by a recent opinion poll. (orig./HSCH) [de

Southeastern New Mexico east of the Pecos River is a tectonically stable area with no major fault movements for the past 250 million years. No major tectonic adjustments are expected in the next million years. Minor tectonic adjustments during Triassic time (200 to 180 million years ago) and early Tertiary time (70 million years ago) have resulted in deepening and eastward tilting of the Delaware basin. These tectonic adjustments have resulted in the opening of joints and consequent solution of the upper part of the Salado salt. Compaction of Pennsylvanian and Lower Permian sediments has also contributed to the basin subsidence. This effect has been most severe on the west edge of the basin near the Pecos River and in the southeast edge of the basin adjoining Winkler County, Texas. Recent minor seismic activity is probably the result of petroleum secondary recovery operations. This seismic activity may result in the release of strain and may contribute to the long term tectonic stability of the area

The article describes the utilisation of nuclear energy in the form of 'nuclear long-distance energy'. Heat produced by nuclear fission is bonded to a reversible chemical reaction (cracking gas) which release the heat again at the place of comsumption by catalytic transformation. The article deals in particular with the process of methane cracking/methanisation, the disconnection of the energy (heat) by the methanisation process and the decisive role of the methanisation catalyzers. (orig.) [de

The concept of nuclear-weapon-free zone, as it has developed from political deliberation since mid-1950s, today covers a spectrum of arrangements, geographically ranging from whole continent like Latin America to a corridor in central Europe, and functionally serving the purposes of preventing the spread of nuclear weapons and avoiding nuclear war. Among the nuclear-weapon-free zones proposed but not established, one is now being negotiated and two are subject to investigations published in official reports. These are the proposed zones in ASEAN area, The Middle East and Nordic Europe

Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea

Since the present legal system on nuclear safety regulation has some problems that refer to contents of regulatory provisions, this mid-report has preformed research on the legal basic theory of nuclear safety regulation. And then secondly this report analyzed the problems of each provisions and suggested the revision drafts on the basis of analyzing problems and the undergoing theory of nuclear safety regulation. In order to interpret easily this report finally took the cases of judicial precedents on nuclear safety regulation in USA, Germany, Japan and Korea.

In 2008, occurred in the Spanish plants various events related to the existence on the sites of the Spanish nuclear facilities or areas dotted with radioactive contamination outside the buildings, events that were reported to the Nuclear Safety Council (CSN) in accordance with the provisions of the regulation, as a result of the analysis of those events, the CSN issued in July 2008, a complementary technique INSTRUCTIONAL requiring the implementation of environmental monitoring programs in outdoor areas within sites nuclear tacilities. First, the CSN nuclear facilities referred to the programs and methodologies intended to perform such monitoring, and, in late 2009, reports of program results.

This work intends to make a critical analysis of the emergency plan of the Angra dos Reis Nuclear Power Plants related to appropriate transportation, accommodation and infrastructure for people with special needs

U-233 SpecialNuclear Material (SNM) currently stored at the T-Building Storage Areas A and B must be transported to the SW/R Tritium Complex for repackaging. This SNM is in the form of oxide powder contained in glass jars which in turn are contained in heat sealed double polyethylene bags. These doubled-bagged glass jars have been primarily stored in structural steel casks and birdcages for approximately 20 years. The three casks, eight birdcages, and one pail/pressure vessel will be loaded onto a transport truck and moved over an eight day period. The Preliminary Hazards and Accident Analysis for the on-site transportation and handling of Uranium-233 SpecialNuclear Material, documented herein, was performed in accordance with the format and content guidance of DOE-STD-3009-94, Preparation Guide for US Department of Energy Nonreactor Nuclear Facility Safety Analysis Reports, dated July 1994, specifically Chapter Three, Hazard and Accident Analysis. The Preliminary Hazards Analysis involved detailed walkdowns of all areas of the U-233 SNM movement route, including the T-Building Storage Area A and B, T-Building truck tunnel, and the roadway route. Extensive discussions were held with operations personnel from the Nuclear Material Control Group, Nuclear Materials Accountability Group, EG and G Mound Security and the Material Handling Systems Transportation Group. Existing documentation related to the on-site transportation of hazardous materials, T-Building and SW/R Tritium Complex SARs, and emergency preparedness/response documentation were also reviewed and analyzed to identify and develop the complete spectrum of energy source hazards

The plant's chemists main responsibility is the establishment and monitoring of an adequate water chemistry to minimize corrosion and in PWRs, to control the neutron flux. But this is by no means the only way in which chemical applications contribute to the performance and safety of a NPP during its entire life: The use of special coatings and treatment protects the plant's components from aggressive environmental conditions. The chemical scale removal in steam generators improves the power output of aging plants, helping even to achieve permissions for NPP life extension. The use of special adhesives can replace welding in complicated or high-dose areas, even underwater. And chemical decontamination is used to remove activity from the components of the primary circuit prior to maintenance or replacement works in order to decrease the radiation exposure of the plant's personnel, employing revolutionary methods of waste minimization to limit the amount of generated radioactive waste to a minimum. The AREVA Group, in its pursue of excellence in all stages of the nuclear cycle, has devoted years of research and development to be able to provide the most advanced technological solutions in this field. The awareness of the existing possibilities will help present and future nuclear professionals, chemists and non-chemists alike, to benefit from the years of experience and continuous development in chemical technologies at the service of the nuclear industry. (authors)

The Educational Research Centre (ERC) of the Joint Institute for Nuclear Research is the place of joint activity of the JINR, Moscow State University (MSU) and Moscow Engineering Physical Institute (MEFI) on students training by a broadened circle of specialities with introduction of new educational forms. Active application of medical accelerator beams of the JINR Laboratory of Nuclear Beams becomes a reason for implementation of a new training chair in the MEFI on the JINR base - the Physical methods in applied studies in the medicine chair. For the 'medical physics' trend development in 2003 the workshop on discussion both curricula and teaching methodic by the speciality was held. One the Educational Research Centre main activities is both organization and conducting an international scientific schools and training courses. The International student School 'Nuclear-Physical Methods and Accelerators is the most popular and traditional. The principal aim of these schools and courses is familiarization of students and postgraduates with last achievement and and contemporary problems of applied medical physics. The school audience is a students and postgraduates of ERC, MSU, MEFI, and an institutes of Poland, Hungary, Slovakia, France, Czech and Bulgaria

This article discusses how the latest system of special water purification KPF-30, designed specifically for the fourth power unit of Beloyarskaya nuclear power plant, which has a number of advantages over other water purification systems as chemical-physical and technical-economic, environmental, and other industrial indicators. The scheme covered in this article systems of special water purification involves the use of a hydrocyclone at the preliminary stage of water treatment, as a worthy alternative to ion-exchange filters, which can significantly reduce the volume of toxic waste. The world community implements the project of closing the nuclear fuel cycle, there is a need to improve the reliability of the equipment for safe processes and development of critical and supercritical parameters in the nuclear industry. Essentially, on operated NPP units, the only factor that can cost-effectively optimize to improve the reliability of equipment is the water chemistry. System KPF30 meets the principles and criteria of ecological safety, demonstrating the justification for reagent less method of water treatment on the main stages, in which no formation of toxic wastes, leading to irreversible consequences of environmental pollution and helps to conserve water.

A new approach to Pasquill stability classification is developed using fuzzy set theory, taking into account the natural continuity of the atmospheric stability and providing means to analyse the obtained stability classes. (2 figs.)

Full Text Available Papillomavirus E2 is a multifunctional viral protein that regulates many aspects of the viral life cycle including viral episome maintenance, transcriptional activation, and repression. E2 is degraded by the ubiquitin-proteasome pathway. Cellular bromodomain protein Brd4 has been implicated in the stabilization of the E2 protein. E2 normally shuttles between the cytoplasm and the nucleus. In this study, we demonstrate that E2 ubiquitylation mostly occurs in the cytoplasm. We also find that the interaction with Brd4 promotes nuclear retention of papillomavirus E2 proteins and contributes to their stabilization in the nucleus. Compared to wild type E2 proteins, nuclear-localization-defective mutants are rapidly degraded by the ubiquitin-proteasome pathway; however, co-expression of Brd4 redirects these mutants into the nucleus and significantly increases their stability. We further demonstrate that tethering E2 proteins to chromatin as either double-bromodomain fusion proteins or histone 2B (H2B fusion proteins significantly stabilizes the E2 proteins. Our studies suggest that chromatin recruitment of the E2 protein via interaction with Brd4 prevents E2 ubiquitylation and proteasomal degradation in the cytoplasm, leading to its stabilization in the nucleus. These studies bring new insights for understanding Brd4-mediated E2 stabilization, and provide an additional mechanism by which the chromatin-associated Brd4 regulates E2 functions.

Forensic science uses the basic principles of all physical and natural science and have evolved many domain of its owns, like Anthropometry, fingerprint, Foot print, ballistics, documentation, Forensic Biology and Serology, Forensic Chemistry, Nuclear forensic science, Forensic Physic, Toxicology, Odontology, Forensic DNA, Cyber Forensic, Forensic Psychology, Forensic engineering etc., which provides a fool prove scientific aid to criminal justice administration. Nuclear forensic science is a fairly young discipline and only a small number of laboratories are active practitioners. However, the number of incidents of illicit trafficking reported and furthermore, the threat of nuclear terrorism calls for preparedness and for effective tools providing hints on the origin of the material and thus on the perpetrator. The determination of characteristic parameters is subject to ongoing research and development work in a number of nuclear measurement laboratories. Parameters like isotopic composition, chemical impurities, age of the material, macroscopic parameters and microstructure provide clues on the origin and on the intended use of the material. Today, nuclear forensics has reached a high degree of maturity and it is highly relevant in the areas of non-proliferation and of nuclear security. Continued development activities and strengthened international cooperation will be of key importance for the perfection of the discipline of nuclear forensics

This document describes a project to use epidemiological studies of workers in the nuclear industry to estimate the cancer risk associated with low-dose chronic exposure to ionizing radiation. The project aims both to improve the basis for radiation risk assessment and to test the validity of currently used models for the extrapolation of radiation risk. This report focusses on the former aim, and summarizes discussions at two meetings held in June 1988. One of these was a small working group consisting mainly of epidemiologists who had carried out studies of nuclear workers; the other included nominees of the nuclear industries of eleven countries as well as epidemiologists and radiation physicists and biologists. As a result of the meetings, efforts are underway to pool existing data and a feasibility study is addressing the possibility of an international collaborative study of unstudied groups of nuclear workers

Since October 2010, the site of the former Kahl Experimental Nuclear Power Station (VAK) has been returned to the desired green-field condition. A special chapter in the German history of the use of nuclear power, which has played a major role in the technical and economic development of this energy resource, has come to an end after 52 years. When nuclear power pioneer Heinrich Mandel ordered VAK from AEG in 1958, the mood associated with using this source of energy was different from what it is now. Politicians of all parties were euphoric about the use of nuclear power, while power plant operators were more reluctant. Finally, also RWE was convinced and planned the construction of VAK as a joint venture with the Bayernwerk AG (now E.ON) utility in Grosswelzheim, Bavaria. The objective was clear: 'The order was placed so that the atomic power plant to be built could be used to accumulate experience in planning, operation, in capital cost and operating cost.' After a construction period of only 29 months, VAK was commissioned on November 13, 1960 as the first German nuclear power plant. The US-designed boiling water reactor had been designed for a power of 16,000 kilowatt. After synchronization with the power grid, the first electricity produced from nuclear power in Germany was fed into the interconnected grid system on June 17, 1961. In its 25 years of operation, VAK proved to be a valuable experimental facility. The plant was decommissioned on November 25, 1985 as planned. In order to maintain its experimental character also beyond the operating phase, the operators had agreed from the beginning to demolish VAK completely to green-field conditions immediately after the end of operations. This became official on May 17, 2010, when the plant was released from the scope of the Atomic Energy Act and was granted a permit for demolition under conventional building law. (orig.)

example, the total neutron cross section (or reaction probability) at 10 MeV consistently decreases with atomic weight from lead to iron to calcium to... Competition among states endures, but instead of a single nuclear adversary, the United States is now threatened by the potential spread of nuclear...is met with a large vessel on the water which is considered to be a concentrated amount of iron (generally) surrounded by the lower atomic number

This Order by the Minister of Industry, Commerce and Crafts and the Minister of Labour was made in implementation of Section 40 of Decree No. 75-306 of 28 April 1975 on the protection of workers against the hazards of ionizing radiation in large nuclear installations. It lays down the safety measures applicable to nuclear reactors and ancillary facilities, particle accelerators, irradiated fuel reprocessing plants and facilities for the storage of radioactive waste. (NEA) [fr

MODES SNM project aimed to carry out technical research in order to develop a prototype for a mobile, modular detection system for radioactive sources and SpecialNuclear Materials (SNM). Its main goal was to deliver a tested prototype of a modular mobile system capable of passively detecting weak or shielded radioactive sources with accuracy higher than that of currently available systems. By the end of the project all the objectives have been successfully achieved. Results from the laboratory commissioning and the field tests will be presented. (authors)

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II specialnuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage

The Department of Energy (DOE) has prepared an environmental assessment (EA), DOE/EA -- 1060, for the consolidation, processing, and interim storage of Category I and II specialnuclear material (SNM) in Building 371 at the Rocky Flats Environmental Technology Site (hereinafter referred to as Rocky Flats or Site), Golden, Colorado. The scope of the EA included alternatives for interim storage including the no action alternative, the construction of a new facility for interim storage at Rocky Flats, and shipment to other DOE facilities for interim storage.

With the end of the Cold War and the accelerated dismantlement of nuclear weapons, the nuclear material inventory of the United States is growing. In addition, the United States has offered these excess weapons-grade nuclear material assets for international inspections with the intent of encouraging reciprocal action by other nations. In support of this policy, Sandia National Laboratories has initiated a pilot effort (Project Straight-Line) to develop a flexible, site-independent system to continuously and remotely monitor stored nuclear material and integrate the collection, processing, and dissemination of information regarding this material to ensure that declared nuclear materials placed in storage remain in place, unaltered, and stable. As part of this effort, a +3.6V battery powered, modular sensor pack has been developed to monitor total radiation dose, radiation dose rate, and the temperature of each nuclear material container and to provide this information using a standardized sensor interface. This paper will discuss the development of the sensors, the engineering and production of the sensor pack units, and their installation and operation at sites in New Mexico, California, and the Pantex plant in Amarillo

The structure and stability of accretion disks composed of hydrogen-rich matter rotating about a central neutron star have been investigated for known sources of viscosity. Two general classes of solutions have been found. For one class the energy generated in the disk is provided by hydrogen burning, whereas for the other class the gravitational binding energy released by viscous dissipation dominates. The former solutions are thermally unstable (stable) whenever hydrogen burns via the normal CNO cycle ( pp chain) in a partially or fully degenerate region of the disk. Solutions characterized by nuclear burning via the β-limited CNO cycle or by viscous dissipation only are always stable. On the basis of a local analysis it is shown that modulations of the mass flow in the disk are possible for a range of mass inflow rates into the disk. In such circumstances the disk can undergo a phase transition from a cold, low-viscosity state to a hot, high-viscosity state as a result of the thermonuclear flash instability. Phase transitions from the hot state to the cold state also occur whenever the mass input rate into the disk is less than the equilibrium mass flow rate corresponding to the hot state. It is also shown that for sufficiently high mass flow rates all the hydrogen-rich matter can be processed to helium in the inner regions of the disk before it can be accreted by a neutron star

The non-random organization of the eukaryotic cell nucleus and the folding of genome in chromatin more or less condensed can influence many functions related to DNA metabolism, including genome stability. Double-strand breaks (DSBs) are the most deleterious DNA damages for the cells. To preserve genome integrity, eukaryotic cells thus developed DSB repair mechanisms conserved from yeast to human, among which homologous recombination (HR) that uses an intact homologous sequence to repair a broken chromosome. HR can be separated in two sub-pathways: Gene Conversion (GC) transfers genetic information from one molecule to its homologous and Break Induced Replication (BIR) establishes a replication fork than can proceed until the chromosome end. My doctorate work was focused on the contribution of the chromatin context and 3D genome organization on DSB repair. In S. cerevisiae, nuclear organization and heterochromatin spreading at sub-telomeres can be modified through the overexpression of the Sir3 or sir3A2Q mutant proteins. We demonstrated that reducing the physical distance between homologous sequences increased GC rates, reinforcing the notion that homology search is a limiting step for recombination. We also showed that hetero-chromatinization of DSB site fine-tunes DSB resection, limiting the loss of the DSB ends required to perform homology search and complete HR. Finally, we noticed that the presence of heterochromatin at the donor locus decreased both GC and BIR efficiencies, probably by affecting strand invasion. This work highlights new regulatory pathways of DNA repair. (author) [fr

Full Text Available Fuel oil flyash (FFA produced in power and water desalination plants firing crude oils in the Kingdom of Saudi Arabia is being disposed in landfills, which increases the burden on the environment, therefore, FFA utilization must be encouraged. In the current research, the effect of adding FFA on the engineering properties of two indigenous soils, namely sand and marl, was investigated. FFA was added at concentrations of 5%, 10% and 15% to both soils with and without the addition of Portland cement. Mixtures of the stabilized soils were thoroughly evaluated using compaction, California Bearing Ratio (CBR, unconfined compressive strength (USC and durability tests. Results of these tests indicated that stabilized sand mixtures could not attain the ACI strength requirements. However, marl was found to satisfy the ACI strength requirement when only 5% of FFA was added together with 5% of cement. When the FFA was increased to 10% and 15%, the mixture’s strength was found to decrease to values below the ACI requirements. Results of the Toxicity Characteristics Leaching Procedure (TCLP, which was performed on samples that passed the ACI requirements, indicated that FFA must be cautiously used in soil stabilization.

A brief review is given of the formation, importance, resources and some unique characteristics of water. A reference has been made about the available water racecourse of Pakistan and urgent need of acquiring additional water resources in the county. Importance of water for energy production and energy for acquiring additional water resources is mentioned. Attractive features and feasibility of nuclear desalination, using dual purpose nuclear power plants are discussed. Criteria for selection of suitable reactor type and desalination process are discussed for desired water to power ratios. The world wide growth of desalination capacity, using various desalination processes are listed. (author)

This report provides and explains the differences between the amounts of nuclear materials charged to DOE facilities and the amounts that could be physically inventoried. This report covers data for the period from October 1, 1979, through March 31, 1980, and includes accounting corrections for data from earlier periods. It is the seventh such semiannual report. These data and explanations, together with the absences of physical indications of any theft attempt, support a finding that during this period no theft or diversion of strategic spcial nuclear material has occurred

.... The phenomenon reflected in this statement is currently manifested in India's nuclear strategy The dawn of the nuclear weapons age in 1945 gave birth to not only a new form of more powerful explosive...

Following Chernobyl accident which has revealed in France a strong need for information on technological risks among population and a lack in its organization, the Mayor of Grenoble City who was also at this time, Environment Minister in French Government had initiated in lsere Region an important operation of consideration of action, which has to been undertaken to correct theses lacks. Among ten actions retained one of them was the creation of an Association for Information of the public for Prevention of major risks. This Association has first initiated a consultation on the perception by the population of the different major risks (Industrial and Naturals) in view of the results of this consultation, Medical Professions were the first concerned and a publication 'Medicine and Nuclear risk' has been elaborated and distributed to all doctors of the Region. A Memento on Nuclear risk as then been written and largely distributed in the region, especially in the medias. A booklet on nuclear risk and behavior in case of nuclear accident has then been realized and distributed to all people around Electronuclear Reactors of the Region and to children in the schools. In complement, public meetings have been organized in these sectors to inform, and discuss with the population. (author)

In electric energy production and consumption, Czechoslovakia holds a remarkable place. Its development after the second world war can be divided into four characteristic periods. The author summarizes the features of the past development and points out the tasks of the future in which the extension of nuclear power plant building plays an important role. (author)

... Plant, Unit 2, Opportunity To Request a Hearing, and Petition for Leave To Intervene, and Commission... Preparation AGENCY: Nuclear Regulatory Commission. ACTION: Notice of acceptance of the license renewal... party as defined in Sec. 2.4 of Title 10 of the Code of Federal Regulations (10 CFR), who believes...

The paper covers the origin of the radioactivity in nuclear power plants, the type of sources (open or sealed) encountered, and their methods of measurement. It covers the problem of personnel dosimetry, including contamination and incorporation, and the administrative methods used to avoid these. It outlines a general work philosophy, as developed in an actual power plant. (orig./RW)

The thermal stability of the French nuclear waste glass was investigated experimentally and by modeling to predict its long-term evolution at low temperature. The crystallization mechanisms were analyzed by studying devitrification in the supercooled liquid. Three main crystalline phases were characterized (CaMoO 4 , CeCO 2 , ZnCr 2 O 4 ). Their crystallisation was TO 4.24 wt%, due to the low concentration of the constituent elements. The nucleation and growth curves showed that platinoid elements catalysed nucleation but did not affect growth, which was governed by volume diffusion. The criteria of classic nucleation theory were applied to determine the thermodynamic and diffusional activation energies. Viscosity measurements illustrate the analogy between the activation energy of viscous flow and diffusion, indicating control of crystallization by viscous flow phenomena. The combined action of nucleation and growth was assessed by TTT plots, revealing a crystallization equilibrium line that enables the crystallized fractions to be predicted over the long term. The authors show that hetero-genetics catalyze the transformation without modifying the maximum crystallized fraction. A kinetic model was developed to describe devitrification in the glass based on the nucleation and growth curves alone. The authors show that the low-temperature growth exhibits scale behavior (between time and temperature) similar to thermo-rheological simplicity. The analogy between the resulting activation energy and that of the viscosity was used to model growth on the basis of viscosity. After validation with a simplified (BaO 2 SiO 2 ) glass, the model was applied to the containment glass. The result indicated that the glass remained completely vitreous after a cooling scenario with the one measured at the glass core. Under isothermal conditions, several million years would be required to reach the maximum theoretical crystallization fraction. (author)

A building project of Radiotherapy and Nuclear Medicine services (diagnostic and therapy), within an Integral Oncology Center (IOC), requires interdisciplinary participation of architects, biomedical engineers, radiation oncologists and medical physicists. This report focus on the medical physicist role in designing, building and commissioning stages, for the final clinical use of an IOC at the Oaxaca High Specialization Regional Hospital (HRAEO). As a first step, during design stage, the medical physicist participates in discussions about radiation safety and regulatory requirements for the National Regulatory Agency (called CNSNS in Mexico). Medical physicists propose solutions to clinical needs and take decisions about installing medical equipment, in order to fulfill technical and medical requirements. As a second step, during the construction stage, medical physicists keep an eye on building materials and structural specifications. Meanwhile, regulatory documentation must be sent to CNSNS. This documentation compiles information about medical equipment, radioactivity facility, radiation workers and nuclear material data, in order to obtain the license for the linear accelerator, brachytherapy and nuclear medicine facilities. As a final step, after equipment installation, the commissioning stage takes place. As the conclusion, we show that medical physicists are essentials in order to fulfill with Mexican regulatory requirements in medical facilities.

A three-day specialised workshop on Nuclear Structure and Decay Data Evaluations was organised and held at the headquarters of the International Atomic Energy Agency in Vienna, Austria, from 27 to 29 April 2015. This workshop covered a wide range of important topics and issues addressed when evaluating and maintaining the Evaluated Nuclear Structure Data File (ENSDF). The primary aim was to improve evaluators’ abilities to identify and understand the most appropriate evaluation processes to adopt in the formulation of individual ENSDF data sets. Participants assessed and reviewed existing policies, procedures and codes, and round-table discussions included the debate and resolution of specific difficulties experienced by ENSDF evaluators (i.e., all workshop participants). The contents of this report constitute a record of this workshop, based on the presentations and subsequent discussions.

Although the element is claimed to be a remarkable corrosion inhibitor for steel, its cost and, more importantly, its radioactivity have prevented technetium being put to any useful industrial purpose. However, when the selection criteria to be applied to radionuclides for in vivo use were being considered, it was discovered that one radionuclide of technetium, namely /sup 99m/Tc, possessed a comparatively rare combination of properties which made it ideal for the organ imaging techniques that were being developed in nuclear medicine. A direct result of the application of /sup 99m/Tc, in conjunction with instruments capable of mapping its distribution within the human body, is the universal acceptance of nuclear techniques in medical diagnosis. Technetium-99m now occupies a position of preeminence as the most frequently used radionuclide in routine clinical practice

In India, the Institute of Nuclear Medicine and Allied Sciences was established with the main objective of developing radioisotopic methodologies for diagnosis, therapy, biomedical research and training. The steady progress in India's atomic energy program gave impetus to rapid growth in the application of nuclear medicine techniques at the Institute and now it is one of the largest users of unsealed radiation sources in the country. Right from the beginning adequate attention has been devoted to the radiation safety of the staff and personnel management techniques have been successfully employed to assess performance of the radiation protection staff. A significant positive correlation (p 0.02) between performance and job satisfaction of radiation protection personnel of the Institute has been demonstrated. Efforts are also directed to evolve a parameter that may throw light on the effectiveness of radiation protection staff and subsequently that may be helpful to monitor the radiation protection program of other establishments

High-level nuclear reactor waste is made up of relatively few long-lived radioactive species, among them plutonium, that contribute to difficulties with its storage and disposal. Separation of these species from larger waste volumes mainly constituting of uranium (about 95 %) coupled with nuclear incineration to fission products of plutonium and the so called minor actinides (Neptunium, Americium, and Curium) and transmutation of some of the long lived fission products to short lived or stable isotopes represents a viable nuclear waste management strategy to drastically reduce the time and space requirements for a bed-rock repository of the remaining waste. A remarkable increase in the international research and development on partitioning and transmutation has occurred during the recent years. The road-map report published in April 2001 by The European Technical Working Group on ADS for the development of a European demonstration facility for nuclear waste transmutation has high-lighted the ongoing European research and pointed out the need for further research. The road-map has given the different research activities a position in the ultimate goal of producing an ADS demonstrator and is guiding research planning on the national as well as on the EU level. The Advanced Accelerator Application (3A) program in the US, with the long term goals to enhance long term public safety, provide benefits for the repository, reduce proliferation risks and improve prospects for nuclear power has focused the research on nuclear waste transmutation. The reports on the 3A program indicates a change of the US former abandonment position towards reprocessing and fast reactors due to a strong incentive to eliminate the reactor plutonium and to lower the amount of high level reactor waste for the Yucca Mountain repository. The SKB's proposed research and development program for the next 3 years (FUD01) was presented by SKB in September 2001. It is proposed that the research program

The US has a non-proliferation policy to receive foreign and domestic research reactor returns of spent fuel materials of US origin. These spent fuel materials are returned to the Department of Energy (DOE) and placed in storage in the L-area spent fuel basin at the Savannah River Site (SRS). The foreign research reactor returns fall subject to the 123 agreements for peaceful cooperation. These ''123 agreements'' are named after section 123 of the Atomic Energy Act of 1954 and govern the conditions of nuclear cooperation with foreign partners. The SRS management of these foreign obligations while planning material disposition paths can be a challenge.

In accordance with successful implementation of the IS in the ROK, the IAEA request the enhanced partnership between the ROK and the IAEA to increase the role of the SSAC(State System of Accounting for and Control of nuclear material) in the ROK. For this reason, the ROK and the IAEA signed the EC(Enhanced Cooperation) arrangement to expand the cooperation area beyond existing LWR enhanced cooperation. The IAEA set up it the one of the EC's objectives to increase the practical use and enhancement of the SSAC. In 2013, the NSSC(Nuclear Safety and Security Committee) formed task force team which included the TSO(Technical Support Organization) staffs and operators to establish scope, object and role of the SSAC for improving it. The improvement of the state safeguards system envisioned in the amendment to the notification is intended to ensure the integrity of the state safeguards with the agreement reached with the IAEA to enhance cooperation, enable facility operators to ensure compliance with their obligatory requirements without assuming unnecessarily duplicate administrative workload, and eliminate unreasonableness of the state accounting and control inspection.

In radiochemical separations progress has been made in developing both discontinuous and continuous separation techniques. Outstanding examples of fast, discontinuous separations have been reported from the University of Mainz where chemical separations are performed on a subsecond time scale. However, when experiments have to be performed repeatedly, a continuous separation process delivering a steady source of short-lived species is more appropriate. Such separations are accomplished in the on-line operating solvent extraction system SISAK. The combination of this separation technique with a Gas Jet Recoil Transport (GJRT) system makes it possible to adapt the separation system to different irradiation facilities. The performance of SISAK has been illustrated through the study of short-lived rare-earth isotopes, using conventional gamma-ray spectroscopy. Following some initial test experiments at a 14 MeV neutron generator in Gothenburg the SISAK system was installed at a Philips PW 5320 neutron generator situated in the Dept. of Nuclear Chemistry, Univ. of Oslo in 1972. In the following two years the main effort was devoted to the development of the experimental separation technique although some physics results were obtained in this period. In 1974 the SISAK system was combined with a GJRT arrangement and installed at the Mainz TRIGA reactor. (JIW)

The evolution of radiation protection in Switzerland caused the Triemli City Hospital to implement building modifications throughout its 13 years of existence which have not been completed todate. However, modest methods allowed to find practicable solutions which largely comply with today's radiation protection regulation. Radiation protection provisions have been rendered more stringent thus resulting in more jobs. At least one additional staff member is required in order to discharge all supervisory functions required like incorporation controls, controls of cleaning and technical staff for their working correctly, contamination controls of floors and working areas, exit controls of special working clothes, etc. The best solution for the hospital would be to have one health physics man specifically commissioned with and employed for radiation protection. (orig./HSCH) [de

A Neutron/Gamma-ray combined inspection system for hidden specialnuclear materials (SNMs) in cargo containers has been developed under a program of Japan Science and Technology Agency in Japan. This inspection system consists of an active neutron-detection system for fast screening and a laser Compton backscattering gamma-ray source in coupling with nuclear resonance fluorescence (NRF) method for precise inspection. The inertial electrostatic confinement fusion device has been adopted as a neutron source and two neutron-detection methods, delayed neutron noise analysis method and high-energy neutron-detection method, have been developed to realize the fast screening system. The prototype system has been constructed and tested in the Reactor Research Institute, Kyoto University. For the generation of the laser Compton backscattering gamma-ray beam, a race track microtron accelerator has been used to reduce the size of the system. For the NRF measurement, an array of LaBr3(Ce) scintillation detectors has been adopted to realize a low-cost detection system. The prototype of the gamma-ray system has been demonstrated in the Kansai Photon Science Institute, National Institutes for Quantum and Radiological Science and Technology. By using numerical simulations based on the data taken from these prototype systems and the inspection-flow, the system designed by this program can detect 1 kg of highly enriched 235U (HEU) hidden in an empty 20-ft container within several minutes.

Waste water treatment methods applied in the purification of waste waters discharged from the laundries are presented. The most usually applied method is vaporization, the most frequently designed procedure is reverse osmosis and ultrafiltration and coagulation. Currently the Nuclear Research Institute in Rez is developing a technology of waste water purification which is aimed at introducing such a method of processing in which a minimum amount of solid wastes will be generated at minimum costs. From the point of view of waste water treatment it is most suitable to wash with soap with an addition of detergent such as sodium alkylaryl sulphonate. A promising preparation is the ROMY suspension. Waste water treatment with the use of coagulation by lime salt, sorption of the residues of organic substances on activated coal and of radionuclide residues on a selective ion exchanger without regeneration should be a sufficiently low-cost and effective technology. (J.P.)

The present invention is in the field of metallurgy. Steels have found an increasing number of applications in mechanical constructions, and notably in the construction of materials for the production of energy and for the fabrication of welded structures operating under pressure at temperatures as high as 450 0 C. A possible application is the pressurized vessels of nuclear facilities. The steels of interest contain carbon, silicon, manganese, nickel, molybdenum, vanadium, aluminium, nitrogen, phosphorus and iron, but are characterized by the fact that they also contain arsenic, tin and calcium. The sum of the weighted percentages of nickel and manganese and the weighted percentage of phosphorous are related as follows: (Ni + Mn) . P [fr

This plan presents the overall objectives, description, justification and planning for the Plutonium Finishing Plant (PFP) Remove SNM Materials. The intent of this plan is to describe how this project will be managed and integrated with other facility stabilization and deactivation activities. This plan supplements the overall integrated plan presented in the Plutonium Finishing Plant Integrated Project Management Plan (IPMP), HNF-3617. This project plan is the top-level definitive project management document for the PFP Remove SNM Materials project. It specifies the technical, schedule, requirements and the cost baseline to manage the execution of the Remove SNM Materials project. Any deviation to the document must be authorized through the appropriate change control process. The Remove SNM Materials project provides the necessary support and controls required for DOE-HQ, DOE-RL, BWHC, and other DOE Complex Contractors the path forward to negotiate shipped/receiver agreements, schedule shipments, and transfer material out of PFP to enable final deactivation

Under special conditions a water-cooled reactor or other multiphase process can be subject to instabilities as the so called density-wave oscillations phenomenon. The purpose of this investigation is to derive the stability limits of a boiling channel for the dynamic response to an inlet velocity perturbation. The solution scheme allowed a coupling for the single and two-phase regions together with a model for the dynamic thermal response of the heated surface. The frequency response of a rational transfer function is obtained and a Nyquist plot is used for stability analysis. The model is, although simplified, quite capable of predicting the threshold for self-excited system or the trends given by more exact solution. (Author) [pt

Two constructive methods for estimating asymptotic stability domains of nonlinear reactor models are described in this paper: Method A based on expansion of a Lyapunov function and Method B based on expansion of any positive definite function. The methods are established on Lyapunov's stability definitions. Method A provides a sequence of stability regions that eventually approaches the exact stability domain, but requires many expansions to obtain the entire stability region because the starting Lyapunov function usually corresponds to a small stability region and because most reactor systems are stiff. Method B requires only a positive definite function and thus it is easy to come up with a starting region. From a large starting region, the entire stability region is estimated effectively after sufficient iterations. It is particularly useful for reactor systems that are stiff. These methods are applied to several nonlinear reactor models known in the literature: one-temperature feedback model, two-temperature feedback model, and xenon dynamics model, and the results are compared. (author)

The evaluation of system stability is an integral part of reactor design. This work focuses on a reduced sodium void worth, metal fueled, liquid metal cooled, fast reactor with a single feedback path associated with the reactor outlet coolant temperature under low reactor power, low reactor coolant flow conditions such as might be found after a loss of flow without scram in some passively safe reactor designs. Stability characterization is performed as system parameters, such as temperature coefficient of reactivity, reactor coolant flow, and natural circulation flow, vary. The system model represents the reactor, the detailed thermal hydraulic reactivity feedback path associated with reactor outlet temperature, and decay heat. The computational procedure consists of a main numeric task which takes input functions generated by auxiliary symbolic preprocessing. In the symbolic stage, transcendental transfer functions are rationalized and introduced in a complex-variable root-locus form of the characteristic equation to yield real polynomial functions. In the MATLAB handled numeric stage, stability is assessed through Routh's algebraic stability criterion. The procedure is applied to reactor cores of different shape and the influence of core geometrical changes on stability regions, stability boundary, stability margin and frequency of oscillation is discussed

Analytical investigations of fluid dynamics problems of relevance to the gaseous core nuclear reactor program are presented. The vortex type flow which appears in the nuclear light bulb concept is analyzed along with the fluid flow in the fuel inlet region for the coaxial flow gaseous core nuclear reactor concept. The development of numerical methods for the solution of the Navier-Stokes equations for appropriate geometries is extended to the case of rotating flows and almost completes the gas core program requirements in this area. The investigations demonstrate that the conceptual design of the coaxial flow reactor needs further development.

PTEN is a PIP3 phosphatase that antagonizes oncogenic PI3-kinase signalling. Due to its critical role in suppressing the potent signalling pathway, it is one of the most mutated tumour suppressors, especially in brain tumours. It is generally thought that PTEN deficiencies predominantly result from either loss of expression or enzymatic activity. By analysing PTEN in malignant glioblastoma primary cells derived from 16 of our patients, we report mutations that block localization of PTEN at the plasma membrane and nucleus without affecting lipid phosphatase activity. Cellular and biochemical analyses as well as structural modelling revealed that two mutations disrupt intramolecular interaction of PTEN and open its conformation, enhancing polyubiquitination of PTEN and decreasing protein stability. Moreover, promoting mono-ubiquitination increases protein stability and nuclear localization of mutant PTEN. Thus, our findings provide a molecular mechanism for cancer-associated PTEN defects and may lead to a brain cancer treatment that targets PTEN mono-ubiquitination.

Important facts about the GSI UNILAC accelerator are reviewed under the special aspects of target and stripper foil applications including general range considerations as seen after the upgrading of the machine to an energy of 20 MeV/u for all ions up to uranium. It is also reported about current works and recent developments in target preparations at GSI divided into four main groups of preparation procedures with sufficient overlap: cold rollings, carbon sublimation-condensations, focussed heavy-ion sputter deposition, and the wide field of high-vacuum evaporation-condensations. Among others, a Ca reduction-distillation procedure is described, a new assembly is shown for sublimation-condensations of uniform C layers of 0.1 to 0.76 mg/cm 2 area densities. A selection of only a few applications of targets at the UNILAC can be given. Improved actinide targets are discussed, in-beam measurements of properties of targets on rotating wheels are explained, and a large-area target wheel with a circumference of nearly one meter is shown. SEM micrographs of damaged targets are given and explained. (orig.)

This report provides a summary of progress for the project ''Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI)'' for the eighteen month period of January 1, 1987 to June 10, 1988. This final report was preceded by the final report for the initial six month period, July 1, 1986 to December 31, 1986 (submitted on January 25, 1987, and revised in June 1987.) Quaternary Tectonics, Geochemical, Mineral Deposits, Vulcanic Geology, Seismology, Tectonics, Neotectonics, Remote Sensing, Geotechnical Assessments, Geotechnical Rock Mass Assessments, Basinal Studies, and Strong Ground Motion

This report provides a summary of progress for the project open-quotes Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI).close quotes A similar report was previously provided for the period of 1 October 1993 to 30 September 1994. The report initially covers the activities of the General Task and is followed by sections that describe the progress of the other ongoing Tasks which are listed below. Task 1: Quaternary Tectonics Task 3: Mineral Deposits, Volcanic Geology Task 4: Seismology Task 5: Tectonics Task 8: Basinal Studies

A major activity of PERLA, the PERformance LAboratory of the Joint Research Center of the European Union is to select, procure and characterize Uranium and Plutonium working reference materials representative of the nuclear materials, subject to safeguards verification measurements by means of increasingly precise NDA techniques. These reference materials ensure the traceability of the measurements back to international standard units. They are used to develop, improve and calibrate the NDA instruments and to train the inspectors to operate these instruments correctly. The paper describes the approach adopted for the procurement, production and characterization plans of LEU standards in the form of UO 2 pellets, U 3 O 8 powders, pins and a mock up PWR fuel element. Homogeneity tests, weighing protocols, humidity checks and impurity analysis were performed on the feed materials (UO 2 powders) and on the final product materials (U 3 O 8 powders and UO 2 pellets). The sampling and the analytical scheme followed for the characterization and the analytical results obtained are presented and statistically evaluated. The characterization of these reference materials carried out by four experienced analytical laboratories allows a certification of the uranium content and isotopic abundance with small confidence intervals in a minimal time and minimal analytical effort

A high-quality materials accounting system and effective international inspections in uranium fuel-fabrication facilities depend heavily upon accurate nondestructive assay measurements of the facility's nuclear materials. While item accounting can monitor a large portion of the facility inventory (fuel rods, assemblies, storage items), the contents of all such items and mass values for all bulk materials must be based on quantitative measurements. Weight measurements, combined with destructive analysis of process samples, can provide highly accurate quantitative information on well-characterized and uniform product materials. However, to cover the full range of process materials and to provide timely accountancy data on hard-to-measure items and rapid verification of previous measurements, radiation-based nondestructive assay (NDA) techniques play an important role. NDA for uranium fuel fabrication facilities relies on passive gamma spectroscopy for enrichment and U isotope mass values of medium-to-low-density samples and holdup deposits; it relies on active neutron techniques for U-235 mass values of high-density and heterogeneous samples. This paper will describe the basic radiation-based nondestructive assay techniques used to perform these measurements. The authors will also discuss the NDA measurement applications for international inspections of European fuel-fabrication facilities

....-Russian relationship. How does China fit into this picture? Are there ways in which "the journey to 2012" envisioned in the Nuclear Posture Review may be disrupted by developments in the strategic triangle...

Full Text Available High reliability and security of power unit are required during operation of power unit while maneuvering. They depend on the stability of reactor when transition from one power level to another. The axial offset is a quantitative measure of the reactor stability. It is shown that change of the active core inlet coolant temperature yields an uncontrollable disturbance affecting the axial offset and therefore the reactor stability. To insure the reactor stability the compromise-combined power control method is proposed. Analysis of the influence of temperature of coolant at the magnitude of the axial offset for different regulatory programs is carried out. The change in the depth of immersion of regulators in the active zone for different regulatory programs when the reactor plant daily capacity maneuver is studied.

Medullary bone deposits serve as a reservoir of labile calcium for egg-shell calcification in birds. Quantitative transmission-electron-microscope methods and light-microscope autoradiographic cell-population-kinetic analyses were used to determine changes in cell-surface specializations and population dynamics of medullary bone osteoclasts during egg-laying in Japanese quail. Prior to egg-shell formation, from 0 to about 8 hours after the previous oviposition, very few osteoclast profiles had ruffled borders. The appearance of ruffled borders coincided with the beginning of egg-shell calcification, about 9-10 hours after the previous oviposition. During egg-shell calcification, about 10-21 hours after the previous oviposition, most osteoclast profiles had ruffled borders. Ruffled borders disappeared at the completion of egg-shell calcification and commencement of egg-shell pigmentation. Thus, functional activities of medullary bone osteoclasts appear to be closely synchronized with egg-shell calcification during egg-laying. From 1 to 48 hours after a single injection of 3H-thymidine (3H-TdR), very few labeled osteoclast nuclei were seen during egg-laying. Following multiple injections of 3H-TdR, the percentage of labeled nuclei reached a peak at about 170 hours after the first injection. At this peak-labeling time, relatively few of the osteoclast profiles that had labeled nuclei had two or more; although the average number of nuclei per osteoclast profile was about 3.6. These kinetic data suggest that the medullary bone osteoclast population has a prolonged rate of turnover compared to rapid changes in cell activities associated with each 24-hour egg-laying cycle; and collectively they would suggest that rapid changes in osteoclast functions occur independently of changes in cell-population dynamics

The text of the Master Agreement Governing Sales of Source, Bye Product and SpecialNuclear Materials for Research Purposes, which has been concluded between the Agency and the Government of the United States of America, is reproduced herein for the information of all Members,

Stabilization techniques for the storage of radioactive wastes are surveyed, with emphasis on immobilization in a primary barrier of synthetic rock. The composition, half-life, and thermal-emission characteristics of the wastes are shown to require thermally stable immobilization enduring at least 100,000 years. Glass materials are determined to be incapable of withstanding the expected conditions, average temperatures of 100-500 C for the first 100 years. The geological-time stability of crystalline materials, ceramics or synthetic rocks, is examined in detail by comparing their components with similar naturally occurring minerals, especially those containing the same radioactive elements. The high-temperature environment over the first 100 years is seen as stabilizing, since it can recrystallize radiation-induced metamicts. The synthetic-rock stabilization technique is found to be essentially feasible, and improvements are suggested, including the substitution of nepheline with freudenbergite and priderite for alkaline-waste stabilization, the maintenance of low oxygen fugacity, and the dilution of the synthetic-rock pellets into an inert medium.

The Hybrid Single Particle Lagrangian Integrated Trajectory (HYSPLIT) model, developed by the National Oceanic and Atmospheric Administration's Air Resources Laboratory, has been configured to simulate the dispersion and deposition of nuclear materials from a surface-based nuclear detonation using publicly available information on nuclear explosions. Much of the information was obtained from "The Effects of Nuclear Weapons" by Glasstone and Dolan (1977). The model was evaluated against the measurements of nuclear fallout from six nuclear tests conducted between 1951 and 1957 at the Nevada Test Site using the global NCEP/NCAR Reanalysis Project (NNRP) and the Weather Research and Forecasting (WRF) meteorological data as input. The model was able to reproduce the general direction and deposition patterns using the coarse NNRP data with Figure of Merit in Space (FMS - the percent overlap between predicted and measured deposition patterns) scores in excess of 50% for four of six simulations for the smallest dose rate contour, with FMS scores declining for higher dose rate contours. When WRF meteorological data were used the FMS scores were 5-20% higher in five of the six simulations, especially at the higher dose rate contours. The one WRF simulation where the scores declined slightly (10-30%) was also the best scoring simulation when using the NNRP data. When compared with measurements of dose rate and time of arrival from the Town Data Base (Thompson et al., 1994), similar results were found with the WRF simulations providing better results for four of six simulations. The overall result was that the different plume simulations using WRF data had more consistent performance than the plume simulations using NNRP data fields. Published by Elsevier Ltd.

In homeland security, neutron detection is used to prevent the smuggling of specialnuclear materials. Thermal neutrons are normally detected with 3 He proportional counters, in the radiation portal monitors, Rpms, however due to the 3 He shortage new procedures are being studied. In this work Monte Carlo methods, using the MCNP6 code, have been used to study the neutron detection features of a 10 B+ZnS(Ag) under real conditions inside of a Rpm. The performance for neutron detection was carried out for 252 Cf, 238 U and 239 Pu under different conditions. In order to mimic an actual situation occurring at border areas, a sample of SNM sited inside a vehicle was simulated and the Rpm with 10 B+ZnS(Ag) response was calculated. At 200 cm the 10 B+ZnS(Ag) on Rpm response is close to 2.5 cps-ng 252 Cf, when the 252 Cf neutron source is shielded with 0.5 cm-thick lead and 2.5 cm-thick polyethylene fulfilling the ANSI recommendations. Three different geometries of neutron detectors of 10 B+ZnS(Ag) in a neutron detection system in Rpm were modeled. Therefore, the 10 B+ZnS(Ag) detectors are an innovative and viable replacement for the 3 He detectors in the Rpm. (Author)

1.1 This test method covers the determination of the concentration of gamma-ray emitting specialnuclear materials dissolved in homogeneous solutions. The test method corrects for gamma-ray attenuation by the solution and its container by measurement of the transmission of a beam of gamma rays from an external source (Refs. (1), (2), and (3)). 1.2 Two solution geometries, slab and cylinder, are considered. The solution container that determines the geometry may be either a removable or a fixed geometry container. This test method is limited to solution containers having walls or a top and bottom of equal transmission through which the gamma rays from the external transmission correction source must pass. 1.3 This test method is typically applied to radionuclide concentrations ranging from a few milligrams per litre to several hundred grams per litre. The assay range will be a function of the specific activity of the nuclide of interest, the physical characteristics of the solution container, counting equip...

Study examined the effect of triangulation on depression in children. Clinical samples and nonclinical samples were taken from Utah and Illinois. Results showed children's depressive symptoms to be most strongly linked to the father's level of marital satisfaction, marital stability, and perceived family triangulation. Mothers' variables did not…

The dynamics of the final stages of the coalescence of two neturon stars (such as the binary pulsar PSR 1913+16) is an unsolved problem in astrophysics. Such systems are probably efficient generators of gravitational radiation, and may be significant contributors to heavy-element nucleosynthesis. The input physics for the study of such systems is similar to that required for the strudy of heavy-ion collision hydrodynamics; e.g., a finite temperature nuclear equation of state, properties of nuclei away from stability, etc. We discuss the development of a relativistic hydrodynamics code in three spatial dimensions for the purpose of studying such neutron-star systems. The properties of the mass-radius relation (determined by the nuclear equation of state) may lead to a proposed mechanism by which hot, highly neutronized matter is ejected from the coalescing stars. This material is photodisintegrated into a free (mostly) neutron gas which may subsequently experience rapid-neutron capture (r-process) nucleosynthesis. 15 refs., 4 figs

Seventy-three papers are included, arranged under the following section headings: national programs for the disposal of radioactive wastes, waste from stability and characterization, glass processing, ceramic processing, ceramic and glass processing, leaching of waste materials, properties of nuclear waste forms, and immobilization of special radioactive wastes. Separate abstracts were prepared for all the papers. (DLC)

Full Text Available In this paper, a nominal SISO (Single Input Single Output model of PHWR (Pressurized Heavy Water Reactor type nuclear power plant is developed based on normal moderator pump-up rate capturing the moderator level dynamics using system identification technique. As the plant model is not exact, therefore additive and multiplicative uncertainty modeling is required. A robust perturbed plant model is derived based on worst case model capturing slowest moderator pump-up rate dynamics and moderator control valve opening delay. Both nominal and worst case models of PHWR-type nuclear power plant have ARX (An Autoregressive Exogenous structures and the parameters of both models are estimated using recursive LMS (Least Mean Square optimization algorithm. Nominal and worst case discrete plant models are transformed into frequency domain for robust controller design purpose. The closed loop system is configured into two port model form and H? robust controller is synthesized. The H?controller is designed based on singular value loop shaping and desired magnitude of control input. The selection of desired disturbance attenuation factor and size of the largest anticipated multiplicative plant perturbation for loop shaping of H? robust controller form a constrained multi-objective optimization problem. The performance and robustness of the proposed controller is tested under transient condition of a nuclear power plant in Pakistan and found satisfactory.

The main objective of this project is to develop an advanced fuel matrix capable of achieving extended burnup while improving safety margins and reliability for present operations. In the course of this project, the authors improve understanding of the mechanism for high burnup structure (HBS) formation and attempt to design a fuel to minimize its formation. The use of soluble dopants in the UO 2 matrix to stabilize the matrix and minimize fuel-side corrosion of the cladding is the main focus

Positive influence of the burnup rate and precipits of the second phase on the fuel stability concerning swelling has been found according to the published results. This paper proposed a dynamic equilibrium model for the precipits state as a function of reactor power density and fuel temperature. It was estimated that the metal fuel can achieve rather high burnup rate in the heavy water power reactors [fr

50 special events were reported in the old Federal States, 47 of them belonged to the reporting category N (normal notification), three to the reporting category E (immediate notification). According to the international evluation scale (INES = International Nuclear Events Scale) five of those events fell under INES category 1, the rest under category 0. The Greifswald nuclear power plant reported three events of category AE-3 (lowest category) at KGR-5. There was no release of radioactivity involved in these incidents, and there were no effects on man or the environment reported. (HP) [de

Previous work into the space-dependent kinetics of the conceptual nuclear fluidized bed has highlighted the sensitivity of fission power to particle movements within the bed. The work presented in this paper investigates a method of stabilizing the fission power by making it less sensitive to fuel particle movement. Steady-state neutronic calculations are performed to obtain a suitable design that is stable to radial and axial fuel particle movements in the bed. Detailed spatial/temporal simulations performed using the finite element transient criticality (FETCH) code investigate the dynamics of the new reactor design. A dual requirement of the design is that it has a moderate power output of ∼300 MW(thermal)

Full Text Available This paper deals with the seismic stability of the survey areas of potential sites for the deep geological repository of the spent nuclear fuel in the Czech Republic. The basic source of data for historical earthquakes up to 1990 was the seismic website [10]. The most intense earthquake described occurred on September 15, 1590 in the Niederroesterreich region (Austria in the historical period; its reported intensity is Io = 8-9. The source of the contemporary seismic data for the period since 1991 to the end of 2014 was the website [11]. It may be stated based on the databases and literature review that in the period from 1900, no earthquake exceeding magnitude 5.1 originated in the territory of the Czech Republic.

The Cosmic Ray Inspection and Passive Tomography (CRIPT) collaboration is developing a cosmic ray muon tomography system to identify SpecialNuclear Materials (SNM) in cargo containers. In order to gauge the viability of the technique, and to determine the best detector type, GEANT4 was used to simulate the passage of cosmic ray muons through a cargo container. The scattering density estimation (SDE) algorithm was developed and tested with data from these simulations to determine how well it could reconstruct the interior of a container. The simulation results revealed the ability of cosmic ray muon tomography techniques to image spheres of lead-shielded SpecialNuclear Materials (SNM), such as uranium or plutonium, in a cargo container, containing a cargo of granite slabs. (author)

The Waste Receiving and Processing (WRAP) Facility will store uranium and transuranic (TRU) sources and standards for certification that WRAP meets the requirements of the Quality Assurance Program Plan (QAPP) for the Waste Isolation Pilot Plant (WIPP). In addition, WRAP must meet internal requirements for testing and validation of measuring instruments for nondestructive assay (NDA). In order to be certified for WIPP, WRAP will participate in the NDA Performance Demonstration Program (PDP). This program is a blind test of the NDA capabilities for TRU waste. It is intended to ensure that the NDA capabilities of this facility satisfy the requirements of the quality assurance program plan for the WIPP. The PDP standards have been provided by the Los Alamos National Laboratory (LANL) for this program. These standards will be used in the WRAP facility. To internally check the accuracy and sensitivity of the NDA instruments, a further set of sources and standards will also be used by the facility. Each sealed source or standard will be referred to herein as a unit. Various combinations of these units will be placed in test drums and/or boxes which will be subject to their own limits until unloaded. There will be two sealed test drums with five grams of weapons grade plutonium loaded in them. These drums will be appropriately marked and will be subject to the unit limits rather than the drum limits. This analysis shows that the storage and use of specialnuclear material sources and standards within the limited control facility of WRAP (Rooms 101 and 104) is safe from a criticality standpoint. With the form, geometry, and masses involved with this evaluation, a criticality is not possible. The limits given in Section 2 should be imposed on facility operations.

The objective of the symposium was to review the 50 years history of the activities of the IAEA and the current status of nuclear power and fuel cycle in the world and discuss the future vision regarding development and safety of nuclear power and fuel cycle and international cooperation. Topics covered were nuclear power and fuel cycle, nuclear safety and security, non proliferation, and national, regional, and IAEA's challenges for the future

The magnitude of Russian foreign debt, both official bilateral and commercial, compounded by collapse of the Russian economic system, is an obstacle in preventing the Russian Federation from effectively increasing the domestic priority of drawing down its nuclear weapons complex and providing a healthy, competitive environment to its nuclear cities. Debt-for-nature swaps, introduced in the early 1980s, provide debtor nations with a means of converting a portion of foreign debt into local currency, often at steep discounts, to use for purposes such as environmental protection that serve both a domestic and international need. This paper presents the debt-for-nature concept as a model for providing an infusion of funds to further U.S. and international nonproliferation objectives to help stabilize Russian closed city economic conditions through direct work on proliferation problems and remediation of the environment. A specific proposal is presented to demonstrate the utility and efficacy of the dept swap concept through initial collaboration with the city administration of Ozersk. The purpose of the proposal is to facilitate making Ozersk a safe, healthy competitive city, providing useful employment for its scientists and population and converting its superior infrastructure into productive activities.

In the JEAG4601-1987 (Japan Electric Association Guide for earthquake resistance design), either the conventional deterministic method or probabilistic method is used for evaluating the stability of ground foundations and surrounding slopes in nuclear power plants. The deterministic method, in which the soil properties of 'mean ± coefficient x standard deviation' is adopted for the calculations, is generally used in the design stage to data. On the other hand, the probabilistic method, in which the soil properties assume to have probabilistic distributions, is stated as a future method. The deterministic method facilitates the evaluation, however, it is necessary to clarify the relationship between the deterministic and probabilistic methods. In order to investigate the relationship, a simple model that can take into account the dynamic effect of structures, and a simplified method for taking the spatial randomness into account are proposed in this study. As a result, it is found that the shear strength of soil is the most important factor for the stability of grounds and slopes, and the probability below the safety factor evaluated with the soil properties of mean - 1.0 x standard deviation' by the deterministic methods of much lower. (author)

The next great issue on the Russian landscape will be management of its foreign debt. In the near future the United States will be called upon to lead an international program of debt restructuring to assist Russia in overcoming the burden of its debt trap. With debt service obligations equal to 50{percent} of 1999 revenues, Russia has virtually no chance of sustaining a program of economic recovery without debt relief (Hardt, 1999). With some form of debt restructuring a foregone conclusion, Russia, the United States, and world community have a vital stake in searching for creative ways to transform the inevitability of debt restructuring into something of value and constructive to Russia and the problems it faces. This was the rationale behind debt-for-nature swaps which emerged in the early 1980s in Latin American and Eastern Europe as a means of relieving developing nations of their crippling foreign debt. Debt-for-nature swaps served both domestic and international needs by converting a portion of foreign debt, often at steep discounts, into local currency that was then used to fund programs to preserve the environment. The debt swap mechanism provides the prospect of getting something of real value where nothing is expected. The Pacific Northwest National Laboratory (PNNL) has proposed to use the same model to synergistically capitalize defense threat reduction activities and environmental remediation within Russia's closed nuclear cities. Preventing the emigration of nuclear technology, expertise, and hardware from these cities to subnational groups and countries of proliferation concern is one of the world's foremost pressing problems. It is in the best national security interest of the United states to assist Russia in overcoming the legacy of the Cold War by helping to address the catastrophic environmental and public health effects of nuclear production that negatively impact economic stabilization.

The next great issue on the Russian landscape will be management of its foreign debt. In the near future the United States will be called upon to lead an international program of debt restructuring to assist Russia in overcoming the burden of its debt trap. With debt service obligations equal to 50% of 1999 revenues, Russia has virtually no chance of sustaining a program of economic recovery without debt relief (Hardt, 1999). With some form of debt restructuring a foregone conclusion, Russia, the United States, and world community have a vital stake in searching for creative ways to transform the inevitability of debt restructuring into something of value and constructive to Russia and the problems it faces. This was the rationale behind debt-for-nature swaps which emerged in the early 1980s in Latin American and Eastern Europe as a means of relieving developing nations of their crippling foreign debt. Debt-for-nature swaps served both domestic and international needs by converting a portion of foreign debt, often at steep discounts, into local currency that was then used to fund programs to preserve the environment. The debt swap mechanism provides the prospect of getting something of real value where nothing is expected. The Pacific Northwest National Laboratory (PNNL) has proposed to use the same model to synergistically capitalize defense threat reduction activities and environmental remediation within Russia's closed nuclear cities. Preventing the emigration of nuclear technology, expertise, and hardware from these cities to subnational groups and countries of proliferation concern is one of the world's foremost pressing problems. It is in the best national security interest of the United states to assist Russia in overcoming the legacy of the Cold War by helping to address the catastrophic environmental and public health effects of nuclear production that negatively impact economic stabilization

Full Text Available Abstract Background Somatic cell nuclear transfer (SCNT provides an appealing alternative for the preservation of genetic material in non-domestic and endangered species. An important prerequisite for successful SCNT is the availability of good quality donor cells, as normal embryo development is dependent upon proper reprogramming of the donor genome so that embryonic genes can be appropriately expressed. The characteristics of donor cell lines and their ability to produce embryos by SCNT were evaluated by testing the effects of tissue sample collection (DART biopsy, PUNCH biopsy, post-mortem EAR sample and culture initiation (explant, collagenase digestion techniques. Results Differences in initial sample size based on sample collection technique had an effect on the amount of time necessary for achieving primary confluence and the number of population doublings (PDL produced. Thus, DART and PUNCH biopsies resulted in cultures with decreased lifespans (50 PDL and chromosomally stable (>70% normal cells at 20 PDL cultures produced by post-mortem EAR samples. Chromosome stability was influenced by sample collection technique and was dependent upon the culture's initial telomere length and its rate of shortening over cell passages. Following SCNT, short-lived cultures resulted in significantly lower blastocyst development (≤ 0.9% compared to highly proliferative cultures (11.8%. Chromosome stability and sample collection technique were significant factors in determining blastocyst development outcome. Conclusion These data demonstrate the influence of culture establishment techniques on cell culture characteristics, including the viability, longevity and normality of cells. The identification of a quantifiable marker associated with SCNT embryo developmental potential, chromosome stability, provides a means by which cell culture conditions can be monitored and improved.

This report is focused on the effects of climate changes on the chemical composition of deep groundwaters. The aim of the work has been to assess the hydrochemical stability at nuclear repository sites in Finland and Sweden. Sites investigated by SKB and POSIVA have been compared. The corresponding features are important in judging how sensitive a site might be to climatic changes. Evidence for climate effects in the past on groundwater compositions has been reviewed, including isotopic and mineralogical data. There is for example evidence that glacial meltwaters are currently present at repository depths in the Fennoscandian Shield. No evidence has been found however that oxidising conditions have ever prevailed at depth, even if glacial meltwaters presumably had a substantial amount of dissolved 0{sub 2}. The depth distribution of different calcite types (and other fracture minerals) indicates stability in large-scale groundwater circulation over time. Information on past (and future) groundwater salinities has been sought after in the results of hydrological numerical models for Aespoe in Sweden and Olkiluoto in Finland. It is expected that groundwater salinities will change due to future climatic variations. The main effects will be from shoreline movements, permafrost and continental ice-sheets. In most sites the present reducing redox conditions will remain undisturbed during glacial cycles. The modelling indicated that most of the SKB suitability criteria will be met during the life-span of the repository and the groundwater composition will vary within what is observed in the samples collected today at various depths. The expected changes are therefore not judged to threaten the integrity and functioning of the repository. The major conclusion is that despite long-term hydrodynamic changes hydrochemical stability is expected to dominate at repository depth. (orig.)

This report is focussed on the effects of climate changes on the chemical composition of deep groundwaters. The aim of the work has been to assess the hydrochemical stability at nuclear repository sites in Finland and Sweden. Sites investigated by SKB and POSIVA have been compared. The corresponding features are important in judging how sensitive a site might be to climatic changes. Evidence for climate effects in the past on groundwater compositions has been reviewed, including isotopic and mineralogical data. There is for example evidence that glacial meltwaters are currently present at repository depths in the Fennoscandian Shield. No evidence has been found however that oxidising conditions have ever prevailed at depth, even if glacial meltwaters presumably had a substantial amount of dissolved O 2 . The depth distribution of different calcite types (and other fracture minerals) indicates stability in large-scale groundwater circulation over time. Information on past (and future) groundwater salinities has been sought after in the results of hydrological numerical models for Aespoe in Sweden and Olkiluoto in Finland. It is expected that groundwater salinities will change due to future climatic variations. The main effects will be from shoreline movements, permafrost and continental ice-sheets. In most sites the present reducing redox conditions will remain undisturbed during glacial cycles. The modelling indicated that most of the SKB suitability criteria will be met during the life-span of the repository and the groundwater composition will vary within what is observed in the samples collected today at various depths. The expected changes are therefore not judged to threaten the integrity and functioning of the repository. The major conclusion is that despite long-term hydrodynamic changes hydrochemical stability is expected to dominate at repository depth

The unprecedented decline of biodiversity worldwide is urging scientists to collect and store biological material from seriously threatened animals, including large mammals. Lyophilization is being explored as a low-cost system for storage in bio-banks of cells that might be used to expand or restore endangered or extinct species through the procedure of Somatic Cell Nuclear Transfer (SCNT). Here we report that the genome is intact in about 60% of lyophylized sheep lymphocytes, whereas DNA damage occurs randomly in the remaining 40%. Remarkably, lyophilized nuclei injected into enucleated oocytes are repaired by a robust DNA repairing activity of the oocytes, and show normal developmental competence. Cloned embryos derived from lyophylized cells exhibited chromosome and cellular composition comparable to those of embryos derived from fresh donor cells. These findings support the feasibility of lyophylization as a storage procedure of mammalian cells to be used for SCNT.

Nuclear transfer (NT) into mouse oocytes yields a transcriptionally and functionally heterogeneous population of cloned embryos. Most studies of NT embryos consider only embryos at predefined key stages (e.g., morula or blastocyst), that is, after the bulk of reprogramming has taken place. These retrospective approaches are of limited use to elucidate mechanisms of reprogramming and to predict developmental success. Observing cloned embryo development using live embryo cinematography has the potential to reveal otherwise undetectable embryo features. However, light exposure necessary for live cell cinematography is highly toxic to cloned embryos. Here we describe a protocol for combined bright-field and fluorescence live-cell imaging of histone H2b-GFP expressing mouse embryos, to record cell divisions up to the blastocyst stage. This protocol, which can be adapted to observe other reporters such as Oct4-GFP or Nanog-GFP, allowed us to quantitatively analyze cleavage kinetics of cloned embryos.

Full Text Available The unprecedented decline of biodiversity worldwide is urging scientists to collect and store biological material from seriously threatened animals, including large mammals. Lyophilization is being explored as a low-cost system for storage in bio-banks of cells that might be used to expand or restore endangered or extinct species through the procedure of Somatic Cell Nuclear Transfer (SCNT. Here we report that the genome is intact in about 60% of lyophylized sheep lymphocytes, whereas DNA damage occurs randomly in the remaining 40%. Remarkably, lyophilized nuclei injected into enucleated oocytes are repaired by a robust DNA repairing activity of the oocytes, and show normal developmental competence. Cloned embryos derived from lyophylized cells exhibited chromosome and cellular composition comparable to those of embryos derived from fresh donor cells. These findings support the feasibility of lyophylization as a storage procedure of mammalian cells to be used for SCNT.

Nuclear power is in the focus of politics and public attention in Germany not only because of the federal elections. Again and again, voices are heard which doubt the decision taken in 2000 to opt out of the use of nuclear power. The change in parliamentary majority in favor of the alliance of CDU/CSU and FDP as a result of the elections on September 27 is leading to another review of the opt-out decision, as the three parties in their platforms expressed themselves in favor of extending nuclear power plant life. This makes a stocktaking exercise of all salient arguments imperative at the present juncture. The perspective in that case should not be restricted to national aspects but include especially the influence of the European dimension of the subject. Present political positions in the 27 EU countries indicate a renaissance of nuclear power. Numerous countries, such as Italy, Sweden, Poland or the United Kingdom, revoked their historic opt-out decisions, are using nuclear power for the first time, or want to expand greatly the nuclear share in their electricity generation mix. All 3 European agencies with clear majorities advocate the extensive use of nuclear power as a long-term component of the mix of energy resources. Germany, with its decision to opt out of the use of nuclear power, is part of a minority. Being part of a European electricity market which will grow together more and more closely up to complete integration, Germany will always be supplied electricity from nuclear sources in the long run. This will be true irrespective of nuclear power plants being operated in the country. So, shutting down German nuclear power plants will not achieve the goals of nuclear opponents but merely give rise to additional challenges in power technology in an effort to ensure Germany's electricity supply. For this reason, the new German federal government should revoke the decision to opt out of the peaceful use of nuclear power. (orig.)

We have developed a new multifunctional, non-viral gene delivery platform consisting of cationic poly(amine-co-ester) (PPMS) for DNA condensation, PEG shell for nanoparticle stabilization, poly(γ-glutamic acid) (γ-PGA) and mTAT (a cell-penetrating peptide) for accelerated cellular uptake, and a nuclear localization signal peptide (NLS) for enhanced intracellular transport of DNA to the nucleus. In vitro study showed that coating of the binary PPMS/DNA polyplex with γ-PGA promotes cellular uptake of the polyplex particles, particularly by γ-glutamyl transpeptidase (GGT)-positive cells through the GGT-mediated endocytosis pathway. Conjugating PEG to the γ-PGA led to the formation of a ternary PPMS/DNA/PGA-g-PEG polyplex with decreased positive charges on the surface of the polyplex particles and substantially higher stability in serum-containing aqueous medium. The cellular uptake rate was further improved by incorporating mTAT into the ternary polyplex system. Addition of the NLS peptide was designed to facilitate intracellular delivery of the plasmid to the nucleus--a rate-limiting step in the gene transfection process. As a result, compared with the binary PPMS/LucDNA polyplex, the new mTAT-quaternary PPMS/LucDNA/NLS/PGA-g-PEG-mTAT system exhibited reduced cytotoxicity, remarkably faster cellular uptake rate, and enhanced transport of DNA to the nucleus. All these advantageous functionalities contribute to the remarkable gene transfection efficiency of the mTAT-quaternary polyplex both in vitro and in vivo, which exceeds that of the binary polyplex and commercial Lipofectamine™ 2000/DNA lipoplex. The multifunctional mTAT-quaternary polyplex system with improved efficiency and reduced cytotoxicity represents a new type of promising non-viral vectors for the delivery of therapeutic genes to treat tumors.We have developed a new multifunctional, non-viral gene delivery platform consisting of cationic poly(amine-co-ester) (PPMS) for DNA condensation, PEG shell

Individual niche specialization (INS) is increasingly recognized as an important component of ecological and evolutionary dynamics. However, most studies that have investigated INS have focused on the effects of niche width and inter- and intraspecific competition on INS in small-bodied species for short time periods, with less attention paid to INS in large-bodied reptilian predators and the effects of available prey types on INS. We investigated the prevalence, causes, and consequences of INS in foraging behaviors across different populations of American alligators (Alligator mississippiensis), the dominant aquatic apex predator across the southeast US, using stomach contents and stable isotopes. Gut contents revealed that, over the short term, although alligator populations occupied wide ranges of the INS spectrum, general patterns were apparent. Alligator populations inhabiting lakes exhibited lower INS than coastal populations, likely driven by variation in habitat type and available prey types. Stable isotopes revealed that over longer time spans alligators exhibited remarkably consistent use of variable mixtures of carbon pools (e.g., marine and freshwater food webs). We conclude that INS in large-bodied reptilian predator populations is likely affected by variation in available prey types and habitat heterogeneity, and that INS should be incorporated into management strategies to efficiently meet intended goals. Also, ecological models, which typically do not consider behavioral variability, should include INS to increase model realism and applicability.

Full Text Available Purpose: to determine stability of the vestibular analyzer of basketball players of the team of KhSAPC by indicators of somatic displacements after the standard vestibular irritations on the Barany chair, after the introduction of the special exercises in the educational – training process, which are directed on the increase of stability of the vestibular sensor-based system. Material & Methods: the analysis of references, methods of definition of a functional condition of the vestibular analyzer on indicators of somatic displacements before and after the irritation on the Barany chair, methods of mathematical statistics. 12 boys – basketball players of the men's national team of KhSAPC took part in the researches. Results: somatic indicators of a functional condition of the vestibular analyzer of students – basketball players of the team of KhSAPC, and, their changes under the influence of rotary loadings before the pedagogical experiment are given in the article. Conclusions: the analysis of the results which were received after the experiment showed the considerable improvement of indicators, according to the testing of the motive test (4x9 m (s, hand dynamometry of 100% of a maximum and 50% of a maximum of the right and left hands (р0,05.

Nuclear scans use radioactive substances to see structures and functions inside your body. They use a special ... images. Most scans take 20 to 45 minutes. Nuclear scans can help doctors diagnose many conditions, including ...

Full text: Al 2 O 3 oxide (as some metal oxides) is one of the prospective high-k electro-insulators and construction oxides materials, in particular, for the ceramics fuel material and the first wall of thermonuclear reactor. Besides, this oxide is used widely as an active element or substrate for lasers and MOS systems, as a film coating and receiver of IR-radiation. From here this work is aimed at investigation of radiation stability of the physical properties and structure of Al 2 O 3 oxide after irradiation to a high fluence in the reactor. In this connection the peculiarities of radiation effect on lattice parameters (a,c), form and position of several reflections, reflection coefficient and frequency of valence and deformation oscillations of Al-O bonds, electric characteristics of the oxide were studied with techniques of X-diffraction, dielectric and IR-reflection spectroscopy. For example, this communication presents the results on X-ray structure investigation of σ after irradiation to high neutron doses (F). X-diffraction patterns were obtained using a roentgen diffractometer. Particular attention was paid to dynamics of form and positions some representative reflexes. The diffraction patterns showed essential changes of peak intensity and position depending upon F, the Bragg angle 2 Θ decreases with an increase in dose, the lattice parameters of crystals ( a, c ) was undergone anisotropy expansion, at very high dose of change this parameters is not so much as Δc= 0,0038 nm and Δa = 0,0014 nm. Besides, it is shown that at these doses some halo appears at the diffraction patterns. The mechanism of atom displacement out of lattice knots plays the main role in radiation damage of crystals irradiated to high doses. The optical characteristics - a reflection coefficient and frequency of valence (736, 614 cm -1 ) and deformation (464 cm -1 ) oscillations of Al-O bonds of the oxide were studied with techniques of IR-reflection spectroscopy in region of

This Functional Design Criteria (FDC) contains information to guide the design of the Stabilization and Packaging Equipment necessary to oxidize and package the remaining plutonium-bearing SpecialNuclear Materials (SNM) currently in the Plutonium Finishing Plant (PFP) inventory. The FDC also guides the design of vault modifications to allow storage of 3013 packages of stabilized SNM for up to 50 years.

This report provides a summary of progress for the project ''Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI)'' for the eighteen month period of January 1, 1987 to June 10, 1988. This final report was preceded by the final report for the initial six month period, July 1, 1986 to December 31, 1986 (submitted on January 25, 1987, and revised in June 1987). The general Task continued to coordinate project activities to meet general deadlines and responsibilities. The central office provided general secretarial support. The activities that were started during the first project period included expansion of the central copying facilities, growth of the central reprint, map, aerial and photograph collections, and some expansion of personal computer capabilities. The research and review accomplishments are mainly under the following tasks: quaternary tectonics, geochemical, mineral deposits, volcanic geology, seismology, tectonics, neotectonics, remote sensing, geotechnical assessments, geotechnical rock mass assessment, basinal studies, and strong ground motion

A lack of understanding is felt in Lithuania of the importance of informing the public about nuclear energy, its safety and decisions related with nuclear energy in general. our swedish colleagues have noticed this flaw in our work and a joined decision has been taken to start a series of publicity projects. It was decided to work along three lines: a series of programmes on the national TV, support to the media of the town of Visaginas and creating an Internet page on the Ignalina Nuclear Power Plant decommissioning

The International Symposium on "Strangeness in Nuclear and Hadronic Systems (SENDAI08)" was held at the Tohoku University Centennial Hall from Monday, 15th December, through Thursday, 18th December 2008; while a pre-symposium was also organized on 14th December. About 126 scientists participated in SENDAI08, including more than 46 from abroad. The symposium was organized as the third in the SENDAI symposium series on strangeness nuclear physics, which was initiated by the Tohoku University's experimental nuclear physics group in 1998. This time, it is motivated by recent progress of the research on nuclear and hadronic systems involving strangeness degree of freedom, particularly, by beams of electrons and photons at JLab, FINUDA, SPring8, LNS Tohoku, etc. and also at new facilities that will be completed in the near future such as J-PARC, etc.

A Delayed Neutron Counting System (DNCS) has been designed and installed to enhance the ability of Royal Military College of Canada (RMC) to analyze SpecialNuclear Materials (SNM). By detecting and recording delayed neutron counts from SNM samples irradiated by the SLOWPOKE-2 Reactor Facility at RMC, the DNCS is able to determine the masses of multiple fissile nuclei in the samples efficiently and accurately. The system is controlled by LabVIEW software. A separate mathematical program has also been developed to determine the mass of fissile nuclei present in SNM. The DNCS and fissile mass determination program have been validated using powdered UO 2 samples. (author)

Illustrated by many graphs and tables, this report comments and discusses the evolution of opinion surveys performed in France on the perception of nuclear risks through thirty annual IRSN opinion surveys. It appears that the opinion on nuclear is rather steady, and that French people have a rather rational perception of risk hierarchy. The first part outlines that unemployment is the main concern for French people, and that environmental concerns depend on current events. The second part analyses the perception of the nuclear risk with respect to other societal concerns and to other risks, and discusses the evolution of opinion from a quantitative to a qualitative sensitivity. The third part addresses the representations people have of nuclear activities and how they challenge the reality: perception of nuclear plants and of radioactive wastes, fear of a serious accident. The last part deals with issues related to responsibilities, abilities and governance: how actors of nuclear risk management are perceived, and expectations in terms of transparency and opinion plurality

Lawrence Livermore National Laboratory (LLNL) Containment Program performed a review of nuclear test-related data for the Norbo underground nuclear test in U8c to assist in evaluating this legacy site as a test bed for application technologies for use in On-Site Inspections (OSI) under the Comprehensive Nuclear Test Ban Treaty. This request is similar to one made for the Salut site in U8c (Pawloski, 2012b). Review of the Norbo site is complicated because the test first exhibited subsurface collapse, which was not unusual, but it then collapsed to the surface over one year later, which was unusual. Of particular interest is the stability of the ground surface above the Norbo detonation point. Proposed methods for on-site verification include radiological signatures, artifacts from nuclear testing activities, and imaging to identify alteration to the subsurface hydrogeology due to the nuclear detonation. Aviva Sussman from the Los Alamos National Laboratory (LANL) has also proposed work at this site. Both proposals require physical access at or near the ground surface of specific underground nuclear test locations at the Nevada Nuclear Security Site (NNSS), formerly the Nevada Test Site (NTS), and focus on possible activities such as visual observation, multispectral measurements, and shallow and deep geophysical surveys.

The decision by the red-green federal government to opt out of the use of nuclear power has considerable consequences for the power industry and the national economy of Germany. In addition, there are additional burdens resulting from the Renewable Energies Act and the Cogeneration Act. Besides economic aspects, there are ecological benefits to be considered in favor of nuclear power. In addition to renewable energy sources, it is one of the important sources of energy which are free from CO 2 emissions. In opt-out decision also jeopardizes the role of Germany as a partner in international cooperation, with an acknowledged standard of nuclear know-how and a cutting-edge position in technical safety. The approaches towards a future energy supply system were put into specific terms together with the CDU/CSU within the activities of the parliamentary committee of inquiry on 'sustainable Energy Supply Under Conditions of Globalization and Deregulation'. The growing dependence on external energy sources, and the goals of climate protection, are other important tasks of future energy policy within the European framework. The Green Book by the EU Commission constitutes a remarkable basis for discussion in this respect. Current problems connected with nuclear power should be discussed seriously in order for nuclear power to continue successfully to contribute to energy supply in Europe. (orig.) [de

Quite apart from its apparent political obsolescence, the policy of nuclear deterrence is vulnerable to attack for its seemingly obvious immorality. Nuclear war is blatantly immoral, and nuclear deterrence requires a genuine intention to resort to the nuclear retaliation which would precipitate such a war. Therefore, since it is wrong to intend that which is wrong to do, deterrence is immoral. This thesis seeks to examine the nature of the deterrent intention as a means of verifying the soundness of the above deontological argument. This examination is carried out by first suggesting an acceptable notion of intention in general and then, after analysing the views of deterrent intention by other writers, proceeding to demonstrate the uniqueness of that intention. Having done this, and having explored the possibility that deterrence need not contain a genuine intention to retaliate, the thesis moves on to suggest and defend a moral principle which states that endeavours requiring the formation of an immoral intention may nevertheless be moral. Called the Principle of Double Intention (and based on the Principle of Double Effect), it offers a method for the moral assessment of agents who form immoral intentions within larger contexts. By applying this principle to nuclear deterrence, it is demonstrated that agents who undertake such a policy may be morally justified in doing so, provided certain conditions are met. The thesis closes with a refutation of the objection that an agent cannot rationally form an intention (such as that required in deterrence) which he has no reason to carry out.

1.1 This test method describes gamma-ray methods used to nondestructively measure the quantity of 235U, or 239Pu remaining as holdup in nuclear facilities. Holdup occurs in all facilities where nuclear material is processed, in process equipment, in exhaust ventilation systems and in building walls and floors. 1.2 This test method includes information useful for management, planning, selection of equipment, consideration of interferences, measurement program definition, and the utilization of resources (1, 2, 3, 4). 1.3 The measurement of nuclear material hold up in process equipment requires a scientific knowledge of radiation sources and detectors, transmission of radiation, calibration, facility operations and error analysis. It is subject to the constraints of the facility, management, budget, and schedule; plus health and safety requirements; as well as the laws of physics. The measurement process includes defining measurement uncertainties and is sensitive to the form and distribution of the material...

Among the different isotopes of Scandium that can be used in nuclear medicine may be mentioned the 47 Sc and 44 Sc. The first decays by emitting an electron associated with a 159 keV gamma can thus be used either for radiotherapy or TEMP imaging. The 44 Sc (3.97 h) decays in 94.27% in case by emitting a positron, with a γ photon energy equal to 1.157 MeV. This isotope is then an ideal candidate for applications in PET imaging. Currently, the Cyclotron of high energy and high intensity ARRONAX produce 44 Sc and co-produces the isomeric state the 44m Sc (2.44 d). The 44m Sc has properties (E(γ) = 270 keV, 98.8%), which allows to consider its use as a potential in vivo generator. Previous work had demonstrated that the DOTA ligand is most suitable and stable for Sc. This thesis aims; make in evidence the feasibility of the in vivo 44m / 44 Sc generator. Initially a procedure was optimized and validated for the production of 44m / 44 Sc with a high specific activity and chemical purity. Radiolabeling of DOTA conjugated peptides was then developed and optimized. Theoretical and experimental studies have been performed in order to demonstrate the feasibility of 44m / 44 Sc as a potential in vivo generator. Finally, in vitro stability studies on radiolabeled 44m / 44 Sc complexes were performed, followed by biodistribution studies and PET imaging. (author)

Full Text Available Malaria presents a diagnostic challenge in areas where both Plasmodium falciparum and P.vivax are co-endemic. Bivalent Rapid Diagnostic tests (RDTs showed promise as diagnostic tools for P.falciparum and P.vivax. To assist national malaria control programme in the selection of RDTs, commercially available seven malaria RDTs were evaluated in terms of their performance with special reference to heat stability.This study was undertaken in four forested districts of central India (July, 2011- March, 2012. All RDTs were tested simultaneously in field along with microscopy as gold standard. These RDTs were stored in their original packing at 25°C before transport to the field or they were stored at 35°C and 45°C upto 100 days for testing the performance of RDTs at high temperature. In all 2841 patients with fever were screened for malaria of which 26% were positive for P.falciparum, and 17% for P.vivax. The highest sensitivity of any RDT for P.falciparum was 98% (95% CI; 95.9-98.8 and lowest sensitivity was 76% (95% CI; 71.7-79.6. For P.vivax highest and lowest sensitivity for any RDT was 80% (95% CI; 94.9 - 83.9 and 20% (95% CI; 15.6-24.5 respectively. Heat stability experiments showed that most RDTs for P.falciparum showed high sensitivity at 45°C upto 90 days. While for P.vivax only two RDTs maintained good sensitivity upto day 90 when compared with RDTs kept at room temperature. Agreement between observers was excellent for positive and negative readings for both P.falciparum and P.vivax (Kappa >0.6-0.9.This is first field evaluation of RDTs regarding their temperature stability. Although RDTs are useful as diagnostic tool for P.falciparum and P.vivax even at high temperature, the quality of RDTs should be regulated and monitored more closely.

The paper has analyzed different manifestations of terrorism with nuclear weapons and ionizing radiation as a special kind of terrorism. Possibilities that terrorist groups come into possession of nuclear weapons and apply them for terrorist purposes have been analysed. The forms and methods of terrorist activities with nuclear means have been given as well. It has been concluded that nuclear terrorism includes various forms of threats, including not only nuclear weapons but also the sources ...

This work intends to make a critical analysis of the emergency plan of the Angra dos Reis Nuclear Power Plants related to appropriate transportation, accommodation and infrastructure for people with special needs.

The Particular intervention plan (PPI in French) is an emergency plan which foresees the measures and means to be implemented to address the potential risks of the presence and operation of a nuclear facility. This plan is implemented and developed by the Prefect in case of nuclear accident (or incident leading to a potential accident), the impact of which extending beyond the facility perimeter. It represents a special section of the organisation plan for civil protection response (ORSEC plan). The PPI foresees the necessary measures and means for crisis management during the first hours following the accident and is triggered by the Department Prefect according to the information provided by the facility operator. Its aim is to protect the populations leaving within 10 km of the facility against a potential radiological hazard. The PPI describes: the facility, the intervention area, the protection measures for the population, the conditions of emergency plan triggering, the crisis organisation, the action forms of the different services, and the post-accident stage. This document is the public version of the Particular intervention plan of the Civaux nuclear power plant (Vienne, France)

The proposed action, the full 5-year renewal of License SNM-1097, is necessary for GE to continue producing fuel used in light-water nuclear reactors. The fuel manufacturing operation principally involves converting UF 6 to UO 2 powder, pressing the UO 2 powder into pellets, sintering and grinding the pellets, loading the pellets into Zircaloy tubes, and then assembling the loaded tubes into fuel bundles. A variety of radiological and nonradiological gaseous, liquid, and solid wastes are generated. After treatment, some of the wastes are released to the environment. In addition to the nuclear fuel fabrication operation, there are other operations performed at GE which do not require NRC licensing (e.g., zirconium metal processing, production of fuel bundle and mechanical reactor components, and the manufacture of aircraft engine parts) and are not associated with the proposed action. 28 references, 15 figures, 21 tables

During the assembly of a product, it is vital that the partially-completed assembly be stable. To guarantee this, one must ensure that contacts among the parts and the fixtures are sufficient to stabilize the assembly. Thus, it would be desirable to have an efficient method for testing an assembly stability, and, if this is not possible, generating a set of additional fixture contact points, known as fixels, that will stabilize it. One can apply this method to the situation of safe handling of specialnuclear material (SNM). To have these functionalities should help improve the safety and enhance the performance of specialnuclear material (SNM) handling and storage operations, since some methods are needed for gripping objects in a stable manner. Also, one may need a way to find a pit-holding fixture inserted into containers. In this paper, the authors present a stability tool, which they call Stab Tool, which was developed to test the stability of objects grasped by robotic hands, objects placed in fixtures, or sets of objects piled randomly on top of one another. Stab Tool runs on top of a commercial software package, TELEGRIP, which is used for geometry modeling and motion creation. The successful development of the stability depends strongly on TELEGRIP`s ability to compute the distances between pairs of three-dimensional bodies in the simulated environment. The interbody distance computation tool takes advantage of the polyhedral representations of bodies used by TELEGRIP and of linear programming techniques to yield an efficient algorithm.

During the assembly of a product, it is vital that the partially-completed assembly be stable. To guarantee this, one must ensure that contacts among the parts and the fixtures are sufficient to stabilize the assembly. Thus, it would be desirable to have an efficient method for testing an assembly stability, and, if this is not possible, generating a set of additional fixture contact points, known as fixels, that will stabilize it. One can apply this method to the situation of safe handling of specialnuclear material (SNM). To have these functionalities should help improve the safety and enhance the performance of specialnuclear material (SNM) handling and storage operations, since some methods are needed for gripping objects in a stable manner. Also, one may need a way to find a pit-holding fixture inserted into containers. In this paper, the authors present a stability tool, which they call Stab Tool, which was developed to test the stability of objects grasped by robotic hands, objects placed in fixtures, or sets of objects piled randomly on top of one another. Stab Tool runs on top of a commercial software package, TELEGRIP, which is used for geometry modeling and motion creation. The successful development of the stability depends strongly on TELEGRIP's ability to compute the distances between pairs of three-dimensional bodies in the simulated environment. The interbody distance computation tool takes advantage of the polyhedral representations of bodies used by TELEGRIP and of linear programming techniques to yield an efficient algorithm

The Babcock and Wilcox Company (B and W) Naval Nuclear Fuel Division (NNFD) facility near Lynchburg, Virginia, produces fuel assemblies and complete fuel modules for reactors used in the US Navy nuclear propulsion program and fuel components for university and other research reactors; and processes scrap material to recover the enriched uranium content. No significant modifications of the production procedures for the US Navy nuclear fuel fabrication have been made since the previous environmental assessment, and none are anticipated during the five-year license renewal period being considered. In 1982 the fabrication of fuel assemblies for university and other research reactors was begun. This environmental assessment provides a review of the past five years of operation and an analysis of future impacts, including the effect of plant changes. The proposed action is the renewal of the license necessary for B and W to continue the existing fuel fabrication operations. Principal operations in the fabrication facility include the processing of highly enriched uranium (> 90% 235 U) into fuel elements and assembling the elements into complete reactor cores for shipment and eventual installation in US Navy facilities. The principal environmental impacts of current operation of the NNFD result from release of radioactive gases to the atmosphere and of radioactively contaminated liquids to the adjacent James River. The actual gaseous and liquid pollutants released during normal operation of the plant have been monitored and documented. The principal subjects addressed in this environmental assessment include water use, pollutant controls, environmental monitoring, and environmental impact of operation and accidents. Other site factors and plant operations necessary for this assessment are described, and aspects of insignificant impacts are identified. 10 figures, 36 tables

After the enlargement of the European Union, Europe has acquired a new dimension which is reflected also on the electricity market. The aggregate European electricity requirement of 3 000 TWh in Europe constitutes approximately one quarter of the world electricity generation. Nuclear power contributes a major share of 966 TWh. In electricity generation from nuclear power, EU-25 is No. 1 in the world. The rising demand for electricity cannot be met by the existing power plant park in the next few decades. Insufficient possibilities of exchange among countries and, especially, the enormous requirement to replace more than 200,000 MW of electricity generating capacity in Europe by 2020, plus another 100,000 MW arising from growing demand, make a comprehensive renewal of the European power plant park indispensable. After the EU enlargement, the standards of the ''old'' European Union are the yardstick for the entire ''new'' Union. This gives rise to enormous efforts, especially in the accession countries, to curb emissions and increase safety. The need for modern power plant technology is becoming particularly apparent in these cases. The example of the ten new member countries clearly shows the options realistically available for electricity generation in the future and indispensable for a favorable infrastructure. The conventional energy resources, i. e. coal, gas, and nuclear power, will be the main sources of electricity generation in Europe over the next few decades. This finding does not meet the expectations of many members of the public who feel that renewables would make the largest contribution to power supply in twenty years' time. This makes it imperative to regain popular acceptance in order to ensure electricity generation at favorable conditions and at a high level of environmental protection in the whole of Europe, with enough leeway to further advance the expansion of renewables and support a positive economic development of Europe. (orig.)

This paper describes general safeguards research being undertaken by the United States Nuclear Regulatory Commission. Efforts to improve the ability of United States licensed plants to contend with the perceived threat of covert material theft are emphasized. The framework for this improvement is to break down the internal control and accounting system into subsystems to achieve material isolation, inventory control, inventory characterization, and inventory containment analysis. A general programme is outlined to develop and evaluate appropriate mechanisms, integrate selected mechanisms into subsystems, and evaluate the subsystems in the context of policy requirements. (author)

An automated x-ray fluorescence (XRF) analysis apparatus and sampling system have been used for a proof-of-principle test of on-line x-ray fluorescence assay of specialnuclear materials (SNM) in dissolver solutions. A ''total sampling'' technique gives total mass assays with no need for solution density or tank volume measurements. Error propagation equations control the accumulation of high-precision data, and are also used for calculating parameters of x-ray fluorescence analysis equipment that will meet specified requirements. Short dwell times at each spectrometer setting significantly compensate for long-term instrumental drift. Sample cells that have survived prolonged exposure to dissolver solution are described. 7 refs., 2 tabs

This regulatory guide describes the information required in the physical security plan submitted as part of an application for a license to possess, use, or transport SpecialNuclear Materials (SNM) of moderate strategic significance or 10 kg or more of SNM of low strategic significance and recommends a standard format for presenting the information in an orderly arrangement. This standard format will thus serve as an aid to uniformity and completeness in the preparation and review of the physical security plan of the license application. This document can also be used as guidance by licensees possessing or transporting less than 10 kg of SNM of low strategic significance in understanding the intent and implementing the requirements of paragraphs 73.67(a), 73.67(f), and 73.67(g) of 10 CFR Part 73

This guide describes the information required in the physical security plan submitted as part of an application for a license to possess, use, or transport specialnuclear material (SNM) of moderate strategic significance or 10 kg or more of SNM of low strategic significance and recommends a standard format for presenting the information in an orderly arrangement. This standards format will thus serve as an aid to uniformity and completeness in the preparation and review of the physical protection plan of the license application. This document can also be used as guidance by licensees possessing or transporting less than 10 kg of SNM of low strategic significance in understanding the intent and implementing the requirements of paragraphs 73.67(a), 73.67(f), and 73.67(g) of 10 CRF Part 73

The detonation of a terrorist nuclear weapon in the United States would result in the massive loss of life and grave economic damage. Even if a device was not detonated, its known or suspected presence aboard a cargo container ship in a U.S. port would have major economic and political consequences. One possible means to prevent this threat would be to board a ship at sea and search for the device before it reaches port. The scenario considered here involves a small Coast Guard team with strong intelligence boarding a container ship to search for a nuclear device. Using active interrogation, the team would nonintrusively search a block of shipping containers to locate the fissile material. Potential interrogation source and detector technologies for the team are discussed. The methodology of the scan is presented along with a technique for calculating the required interrogation source strength using computer simulations. MCNPX was used to construct a computer model of a container ship, and several search scenarios were simulated. The results of the simulations are presented in terms of the source strength required for each interrogation scenario. Validation measurements were performed in order to scale these simulation results to expected performance. Interrogations through the short (2.4 m) axis of a standardized shipping container appear to be feasible given the entire range of container loadings tested. Interrogations through several containers at once or a single container through its long (12.2 m) axis do not appear to be viable with a portable interrogation system.

The detonation of a terrorist nuclear weapon in the United States would result in the massive loss of life and grave economic damage. Even if a device was not detonated, its known or suspected presence aboard a cargo container ship in a U.S. port would have major economic and political consequences. One possible means to prevent this threat would be to board a ship at sea and search for the device before it reaches port. The scenario considered here involves a small Coast Guard team with strong intelligence boarding a container ship to search for a nuclear device. Using active interrogation, the team would nonintrusively search a block of shipping containers to locate the fissile material. Potential interrogation source and detector technologies for the team are discussed. The methodology of the scan is presented along with a technique for calculating the required interrogation source strength using computer simulations. MCNPX was used to construct a computer model of a container ship, and several search scenarios were simulated. The results of the simulations are presented in terms of the source strength required for each interrogation scenario. Validation measurements were performed in order to scale these simulation results to expected performance. Interrogations through the short (2.4 m) axis of a standardized shipping container appear to be feasible given the entire range of container loadings tested. Interrogations through several containers at once or a single container through its long (12.2 m) axis do not appear to be viable with a portable interrogation system

The author argues as follows: The legislation which currently regulates EIS, does not give any party other than the proponent the possibility of exercising influence over the EIA. Therefore, an extensive review and amendment of the existing legislation is necessary if the general public is to participate in the process. This should be regarded as necessary, if SKB is to gain general acceptance of its work. Work on developing a suitable method and identifying a suitable site is going on, but is not conducted in such a manner that it gives the general public an adequate possibility of participating. Furthermore, decision-makers in the candidate municipalities are not being given insight into the work. A specially established EIA authority, charged with the task of supervising the EIA, may lead to that the problems will be investigated in a better way, that can lead to the selection of the best method as well as the best site

In the fourth concluding article on this subject (following articles in VW 1981 pp. 483, 552 and 629), the author explains procedures, duties and obligations according to the Para. Para. 5, 6 and 7 of the AHBKA. These obligations are to be observed before or after the occurrence of damages. In addition, legal consequences following violations of duties - loss of right - joint, insurance, transfer ban, period for filing suit, duty to notify, 'The German Nuclear Reactor Insurance and Reinsurance Community', the insurance according to the 'General terms and conditions governing the liability insurance of licensed activities involving nuclear fuels and other radioactive substances outside nuclear installations (AHBStr.)', object, beginning and exclusion of coverage, 'Special conditions governing the transport of nuclear fuels according to Para. 25 (2) of the Atomic Energy Law' are attached to the General Terms and Conditions governing the liability insurance of licenced activities involving nuclear fuels and other radioactive substances outside nuclear installations. (HSCH) [de

The recommendations contained throughout this NUREG were provided to the Nuclear Regulatory Commission (NRC) as medical screening information that could be used by physicians who are evaluating the parameters of the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The medical recommendations in this NUREG are similar in content to the medical standards contained in 10 CFR Part 1046 which, in part, specifies medical standards for the protective force personnel regulated by the Department of Energy. The guidelines contained in this NUREG are not requirements, and compliance is not required. 3 refs.

The recommendations contained throughout this NUREG were provided to the Nuclear Regulatory Commission (NRC) as medical screening information that could be used by physicians who are evaluating the parameters of the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The medical recommendations in this NUREG are similar in content to the medical standards contained in 10 CFR Part 1046 which, in part, specifies medical standards for the protective force personnel regulated by the Department of Energy. The guidelines contained in this NUREG are not requirements, and compliance is not required. 3 refs

The recommendations contained throughout this NUREG are being provided to the Nuclear Regulatory Commission (NRC) as a reference manual which can be used by licensee management as they develop a program plan for the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The recommendations in this NUREG are similar in part to those contained within the Department of Energy (DOE) Medical and Fitness Implementation Guide which was published in March 1991. The guidelines contained in this NUREG are not requirements, and compliance is not required. 25 refs

The paper was read at the international symposium on nuclear liability held in Munich in September 1984 by OECD/NEA and IAEA. It outlines the basic principles of the Paris liability convention and the international development. The author pleads in favour of unlimited liability for hazards on grounds of history, legal policy, legal dogmatics and practice. Moreover he thinks it useful and appropriate because it also improves the protection of the citizens. The same as the federal government the author holds that unlimited liability for hazards is compatible with the maximum damages and the congruity regulations of the Paris and Brussels liability convention. An amendment to the liability convention, though not necessary, would be desirable to make clear that both options - limited and unlimited liability - are open. (HSCH) [de

The recommendations contained throughout this NUREG are being provided to the Nuclear Regulatory Commission (NRC) as a reference manual which can be used by licensee management as they develop a program plan for the safe participation of guards, Tactical Response Team members (TRTs), and all other armed response personnel in physical fitness training and in physical performance standards testing. The information provided in this NUREG will help licensees to determine if guards, TRTs, and other armed response personnel can effectively perform their normal and emergency duties without undue hazard to themselves, to fellow employees, to the plant site, and to the general public. The recommendations in this NUREG are similar in part to those contained within the Department of Energy (DOE) Medical and Fitness Implementation Guide which was published in March 1991. The guidelines contained in this NUREG are not requirements, and compliance is not required. 25 refs.

A large fraction of the work undertaken jointly by the Commissariat a l'Energie Atomique (CEA) and the Pechiney Company has been the improvement of the properties of nuclear pile graphite and the opening up of new fields of graphite application. New processes for the manufacture of carbons and special graphites have been developed: forged graphite, pyro-carbons, high density graphite agglomeration of graphite powders by cracking of natural gas, impervious graphites. The physical properties of these products and their reaction with various oxidising gases are described. The first irradiation results are also given. (authors) [fr

Biofouling is known to be one of the common problems in cooling water systems of power plants and several incidents of plant shutdown have been reported from various parts of the world. The settlement of marine organisms on an exposed hard surface depends obviously on the species, which are naturally present at a given site as well as their ability to attach and grow on that surface. Information on the organisms forming the fouling complex is necessary in view of the damages they cause to various marine structures and for devising protective measures. The present paper reports the results of the investigations of biofouling carried out for a period of two years from November 2003 to October 2004 at Kudankulam coast where a mega nuclear power project is under construction. Wooden test panels (10x10x3 cm) were fitted to a raft and submerged in the coastal waters. Total fouling biomass, thickness, coverage and community composition were analysed from the panels. Barnacles, mussels, ascidians, polychaetes, amphipods and seaweeds were the common fouling groups settled on the test panels. The total biomass reached to a maximum of 69.9 g.dm -2 (dry weight) after 330 days of exposure. The fouling thickness reached a maximum of 42.3 mm after 225 days of exposure. Results also showed a strong temporal variation in the fouling community recruitment. Based on the observations, Kudankulam coast could be categorized as a moderate fouling station mainly due to the low abundance of mussels in this region. (author)

The design, construction, calibration and testing of a prototype mobile counting system to measure natural uranium in the lungs of workers in the nuclear fuel industry is described. The measurement method is based on the detection of gamma rays emitted during the decay of the daughters of uranium. The mobile facility consisted of a shadow shield and phoswich detector system mounted in a medium-sized trunk. Care was taken to ensure undistorted visual and verbal contact between the subject and the operator. Tests were made to optimize the location and thickness of the lead shielding. A single axle truck was insulated and a heater was installed for winter operation. There was sufficient room in the box to include a change room and waiting area as well as the shadow shield and electronics rack. An extensive series of test measurements was made at a number of locations. Control group studies of males were carried out and a model was developed which correctly predicted the subject background in the uranium region of the gamma spectrum when no uranium was present. The mobile counter was calibrated using the Rando Phantom. On a field trip to Bancroft In February 1981 the shadow shield configuration was shown to provide adequate background reduction for accurate uranium-in-lung measurements. With repeated measurements, changes in an individual's lung burden as small as 2 mg uranium could be detected. The minimum detectable amount of uranium on the basis of one measurement was 5.4 mg

The paper presents an analysis and discussion of the underground ventilation system at the Waste Isolation Pilot Plant (WIPP). Particular emphasis is placed on specific repository-related requirements and the gradual evolution of engineering designs relative to the WIPP Project scope. The ventilation system for a nuclear waste facility similar to WIPP is designed to provide a suitable environment for personnel and equipment during normal activities. It is also designed to provide confinement and channeling of potential airborne radioactive material in the event of an accidental release. It is desirable to identify and design all parallel activities and the required process equipment prior to completion of the repository mine final design. Such factors as ventilation requirements, drift sizes, bulkhead sizes, and placement are dependent on these items. Mine creep closure properties must be factored into the mine and ventilation equipment design considerations. Effects of natural ventilation pressures deserve due consideration in the design. Mine ventilation requirements are dominated by the diesel equipment to be operated in the underground horizon. WIPP engineers have also found it extremely desirable to have automated real-time monitoring and control for the underground ventilation air. Final testing and balancing of the ventilation system is an extremely important startup requirement. 3 refs., 2 figs

This meeting was held on March 4, 1993. Since the first power generation with the JPDR and the initial criticality of the KUR, 30 years, and since the initial criticality of the KUCA, 20 years have elapsed. The researchers in universities have contributed greatly to the research and education of atomic energy, but the perspective of leading the world hereafter in this field is very uncertain. This study meeting was held to seek the way to make the proper contribution. In the meeting, lectures were given on Japanese policy on nuclear fuel cycle, the present state of the upstream research and the downstream research in Japan, the experimental plan in NUCEF, the present state of the researches on TRU decay heat data and TRU nucleus data, the present state of the experimental researches at KUCA and at FCA, the present state of the research on the heat removal from high conversion LWRs and the KUR, the present state of the research on radioactive waste treatment, and the present state of TRU chemical research. The record of the holding of this study meeting is added. (K.I.)

The paper on 'nuclear structure' is the Appendix to the Daresbury (United Kingdom) Annual Report 1985/86, and contains the research work carried out at the Nuclear Structure Facility, Daresbury, within that period. During the year a total of 74 experiments were scheduled covering the main areas of activity including: nuclear collective motion, nuclei far from stability, and nuclear collisions. The Appendix contains brief reports on these experiments and associated theory. (U.K.)

This Quality Assurance Program Plan (QAPP) identifies project quality assurance requirements for all contractors involved in the planning and execution of Hanford Site activities for design, procurement, construction, testing and inspection for Project W-460, Plutonium Stabilization and Handling. The project encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing specialnuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM

Full Text Available An x-ray free-electron laser oscillator (XFELO is a next-generation x-ray source, similar to free-electron laser oscillators at VUV and longer wavelengths but using crystals as high-reflectivity x-ray mirrors. Each output pulse from an XFELO is fully coherent with high spectral purity. The temporal coherence length can further be increased drastically, from picoseconds to microseconds or even longer, by phase-locking successive XFELO output pulses, using the narrow nuclear resonance lines of nuclei such as ^{57}Fe as a reference. We show that the phase fluctuation due to the seismic activities is controllable and that due to spontaneous emission is small. The fluctuation of electron-bunch spacing contributes mainly to the envelope fluctuation but not to the phase fluctuation. By counting the number of standing-wave maxima formed by the output of the nuclear-resonance-stabilized (NRS XFELO over an optically known length, the wavelength of the nuclear resonance can be accurately measured, possibly leading to a new length or frequency standard at x-ray wavelengths. A NRS-XFELO will be an ideal source for experimental x-ray quantum optics as well as other fundamental physics. The technique can be refined for other, narrower resonances such as ^{181}Ta or ^{45}Sc.

The McKinsey group at Yale has been awarded a grant from DTRA for the building of a Liquid Xenon Gamma Ray Color Camera (LXe-GRCC), which combines state-of-the-art detection of LXe scintillation light and time projection chamber (TPC) charge readout. The DTRA application requires a movable detector and hence only a single phase (liquid) xenon detector can be considered in this case. We propose to extend the DTRA project to applications that allow a two phase (liquid/gas) xenon TPC. This entails additional (yet minimal) hardware and extension of the research effort funded by DTRA. The two phase detector will have better energy and angular resolution. Such detectors will be useful for PET medical imaging and detection of specialnuclear material in stationary applications (e.g. port of entry). The expertise of the UConn group in gas phase TPCs will enhance the capabilities of the Yale group and the synergy between the two groups will be very beneficial for this research project as well as the education and research projects of the two universities. The LXe technology to be used in this project has matured rapidly over the past few years, developed for use in detectors for nuclear physics and astrophysics. This technology may now be applied in a straightforward way to the imaging of gamma rays. According to detailed Monte Carlo simulations recently performed at Yale University, energy resolution of 1% and angular resolution of 3 degrees may be obtained for 1.0 MeV gamma rays, using existing technology. With further research and development, energy resolution of 0.5% and angular resolution of 1.3 degrees will be possible at 1.0 MeV. Because liquid xenon is a high density, high Z material, it is highly efficient for scattering and capturing gamma rays. In addition, this technology scales elegantly to large detector areas, with several square meter apertures possible. The Yale research group is highly experienced in the development and use of noble liquid detectors for

In homeland security, neutron detection is used to prevent the smuggling of specialnuclear materials. Thermal neutrons are normally detected with {sup 3}He proportional counters, in the radiation portal monitors, Rpms, however due to the {sup 3}He shortage new procedures are being studied. In this work Monte Carlo methods, using the MCNP6 code, have been used to study the neutron detection features of a {sup 10}B+ZnS(Ag) under real conditions inside of a Rpm. The performance for neutron detection was carried out for {sup 252}Cf, {sup 238}U and {sup 239}Pu under different conditions. In order to mimic an actual situation occurring at border areas, a sample of SNM sited inside a vehicle was simulated and the Rpm with {sup 10}B+ZnS(Ag) response was calculated. At 200 cm the {sup 10}B+ZnS(Ag) on Rpm response is close to 2.5 cps-ng {sup 252}Cf, when the {sup 252}Cf neutron source is shielded with 0.5 cm-thick lead and 2.5 cm-thick polyethylene fulfilling the ANSI recommendations. Three different geometries of neutron detectors of {sup 10}B+ZnS(Ag) in a neutron detection system in Rpm were modeled. Therefore, the {sup 10}B+ZnS(Ag) detectors are an innovative and viable replacement for the {sup 3}He detectors in the Rpm. (Author)

1.1 This test method covers the transmission-corrected nondestructive assay (NDA) of gamma-ray emitting specialnuclear materials (SNMs), most commonly 235U, 239Pu, and 241Am, in low-density scrap or waste, packaged in cylindrical containers. The method can also be applied to NDA of other gamma-emitting nuclides including fission products. High-resolution gamma-ray spectroscopy is used to detect and measure the nuclides of interest and to measure and correct for gamma-ray attenuation in a series of horizontal segments (collimated gamma detector views) of the container. Corrections are also made for counting losses occasioned by signal processing limitations (1-3). 1.2 There are currently several systems in use or under development for determining the attenuation corrections for NDA of radioisotopic materials (4-8). A related technique, tomographic gamma-ray scanning (TGS), is not included in this test method (9, 10, 11). 1.2.1 This test method will cover two implementations of the Segmented Gamma Scanning ...

Musaceae is a small paleotropical family. Three genera have been recognised within this family although the generic delimitations remain controversial. Most species of the family (around 65 species) have been placed under the genus Musa and its infrageneric classification has long been disputed. In this study, we obtained nuclear ribosomal ITS and chloroplast (atpB-rbcL, rps16, and trnL-F) DNA sequences of 36 species (42 accessions of ingroups representing three genera) together with 10 accessions of ingroups retrieved from GenBank database and 4 accessions of outgroups, to construct the phylogeny of the family, with a special reference to the infrageneric classification of the genus Musa. Our phylogenetic analyses elaborated previous results in supporting the monophyly of the family and suggested that Musella and Ensete may be congeneric or at least closely related, but refuted the previous infrageneric classification of Musa. None of the five sections of Musa previously defined based on morphology was recovered as monophyletic group in the molecular phylogeny. Two infrageneric clades were identified, which corresponded well to the basic chromosome numbers of x=11 and 10/9/7, respectively: the former clade comprises species from the sections Musa and Rhodochlamys while the latter contains sections of Callimusa, Australimusa, and Ingentimusa. Copyright 2010 Elsevier Inc. All rights reserved.

Direct disposal of spent nuclear fuel (SNF) in deep geological formations is the preferred option for the final storage of nuclear waste in many countries. In order to assess to which extent radionuclides could be released to the environment, it is of great importance to understand how they are chemically bound in the waste matrix. This is particularly important for long-lived radionuclides such as (79)Se, (129)I, (14)C or (36)Cl, which form poorly sorbing anionic species in water and therefore migrate without significant retardation through argillaceous repository materials and host rocks. We present here X-ray absorption spectroscopic data providing evidence that in the investigated SNF samples selenium is directly bound to U atoms as Se(-II) (selenide) ion, probably replacing oxygen in the cubic UO2 lattice. This result is corroborated by a simple thermodynamic analysis, showing that selenide is the stable form of Se under reactor operation conditions. Because selenide is almost insoluble in water, our data indirectly explain the unexpectedly low release of Se in short-term aqueous leaching experiments, compared to iodine or cesium. These results have a direct impact on safety analyses for potential nuclear waste repository sites, as they justify assuming a small fractional release of selenium in performance assessment calculations.

While GNS casks of the CASTOR family are a suitable means to transfer fuel assemblies (FA) from the NPP to an interim dry storage site, Germanys phase-out of nuclear energy has triggered the demand for an additional solution to dispose of special fuel rods (SFR), normally remaining in the fuel pond until the final shutdown of the NPP. SFR are fuel rods that had to be removed from fuel assemblies mainly due to their special condition, e. g. damages in the cladding of the fuel rods which may have occurred during reactor operations. SFR are usually stored in the spent fuel pond after they are removed from the FA. The quiver for special fuel rods features a robust yet simple design, with a high mechanical stability, a reliable leak-tightness and large safety margins for future requirements on safety analysis. The quiver for special fuel rods can be easily adapted to a large variety of different damaged fuel rods and tailored to the specific need of the customer. The quiver for special fuel rods is adaptable e.g. in length and diameter for use in other types of transport and storage casks and is applicable in other countries as well. The overall concept presented here is a first of its kind solution for the disposal of SFRs via Castor V-casks. This provides an important precondition in achieving the status 'free from nuclear fuel' of the shut down German NPPs

Fail-safe operation of various safeguard devices, operational and auxiliary equipments and control components, e.g. servomotors other engines and various appliances, is required for a safe operation of nuclear power plants. Non-metal materials, control components, motors and other appliances have to be tested and their properties evaluated after γ-irradiation with doses corresponding to the assumed long term radiation commitment and also to the irradiation caused by an eventual accident. The radiation stability of greases used in devices exposed to high doses of the ionizing radiation presents a rather serious and important problem. The results of some tests and the evaluation of the properties of irradiated plastic lubricants are described. (author)

This report provides a summary of progress for the project open-quotes Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI).close quotes A similar report was previously provided for the period of 1 October 1991 to 30 September 1992. The report initially covers the activities of the General Task and is followed by sections that describe the progress of the other ongoing Tasks. This report summarizes the geologic and seismotectonic studies conducted at Yucca Mountain during the contract period including Quaternary tectonics, an evaluation of mineral resource potential of the area, caldera geology, and volcano-tectonic activity at and near the site. A report of basinal studies conducted during the contract period is also included. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database

This report dated 30 September 1992 provides a summary of progress for the project {open_quotes}Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI){close_quotes}. This progress report was preceded by the progress report for the year from 1 October 1990 to 30 September 1991. This report summarizes the geologic and seismotectonic studies conducted at Yucca Mountain during the contract period including Quaternary tectonics, an evaluation of mineral resource potential of the area, caldera geology, and volcano-tectonic activity at and near the site. A report of basinal studies conducted during the contract period is also included. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

This report provides a summary of progress for the project {open_quotes}Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI).{close_quotes} A similar report was previously provided for the period of 1 October 1991 to 30 September 1992. The report initially covers the activities of the General Task and is followed by sections that describe the progress of the other ongoing Tasks. This report summarizes the geologic and seismotectonic studies conducted at Yucca Mountain during the contract period including Quaternary tectonics, an evaluation of mineral resource potential of the area, caldera geology, and volcano-tectonic activity at and near the site. A report of basinal studies conducted during the contract period is also included. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

NUMEL is a computer aided design suite for the assessment of the steady state, static/dynamic stability and transient responses of nuclear steam generators. The equations solved are those of a monotube coflow or counterflow heat exchanger. The advantages of NUMEL are its fast execution speed, robustness, extensive validation and flexibility coupled with ease of use. The code can simultaneously model up to four separate sections (e.g. reheater, HP boiler). This document is a user manual and describes in detail the running of the NUMEL suite. In addition, a discussion is presented of the necessary approximations involved in representing a serpentine or helical AGR boiler as a monotube counterflow heat exchanger. To date, NUMEL has been applied to the modelling of AGR, Fast Reactor and once through Magnox and conventional boilers. Other versions of the code are available for specialist applications, e.g. Magnox and conventional recirculation boilers. (author)

This report dated 30 September 1994 provides a summary of progress for the project {open_quotes}Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI){close_quotes}. This progress report was preceded by the progress report for the year from 1 October 1992 to 30 September 1993. This report summarizes the geologic and seismotectonic studies conducted at Yucca Mountain during the contract period including Quaternary tectonics, an evaluation of mineral resource potential of the area, caldera geology, and volcano-tectonic activity at and near the site. A report of basinal studies conducted during the contract period is also included. Selected papers are indexed separately for inclusion in the Energy Science and Technology Database.

Full Text Available Xylanases belong to an important class of industrial enzymes. Various xylanases have been purified and characterized from a plethora of organisms including bacteria, marine algae, plants, protozoans, insects, snails and crustaceans. Depending on the source, the enzymatic activity of xylanases varies considerably under various physico-chemical conditions such as temperature, pH, high salt and in the presence of proteases. Family 10 or glycosyl hydrolase 10 (GH10 xylanases are one of the well characterized and thoroughly studied classes of industrial enzymes. The TIM-barrel fold structure which is ubiquitous in nature is one of the characteristics of family 10 xylanases. Family 10 xylanases have been used as a “model system” due to their TIM-barrel fold to dissect and understand protein stability under various conditions. A better understanding of structure-stability-function relationships of family 10 xylanases allows one to apply these governing molecular rules to engineer other TIM-barrel fold proteins to improve their stability and retain function(s under adverse conditions. In this review, we discuss the implications of N-and C-terminal interactions, observed in family 10 xylanases on protein stability under extreme conditions. The role of metal binding and aromatic clusters in protein stability is also discussed. Studying and understanding family 10 xylanase structure and function, can contribute to our protein engineering knowledge.

Full Text Available Xylanases belong to an important class of industrial enzymes. Various xylanases have been purified and characterized from a plethora of organisms including bacteria, marine algae, plants, protozoans, insects, snails and crustaceans. Depending on the source, the enzymatic activity of xylanases varies considerably under various physico-chemical conditions such as temperature, pH, high salt and in the presence of proteases. Family 10 or glycosyl hydrolase 10 (GH10 xylanases are one of the well characterized and thoroughly studied classes of industrial enzymes. The TIM-barrel fold structure which is ubiquitous in nature is one of the characteristics of family 10 xylanases. Family 10 xylanases have been used as a “model system” due to their TIM-barrel fold to dissect and understand protein stability under various conditions. A better understanding of structure-stability-function relationships of family 10 xylanases allows one to apply these governing molecular rules to engineer other TIM-barrel fold proteins to improve their stability and retain function(s under adverse conditions. In this review, we discuss the implications of N-and C-terminal interactions, observed in family 10 xylanases on protein stability under extreme conditions. The role of metal binding and aromatic clusters in protein stability is also discussed. Studying and understanding family 10 xylanase structure and function, can contribute to our protein engineering knowledge.

Full Text Available Mild mutations in BRCA2 (FANCD1 cause Fanconi anemia (FA when homozygous, while severe mutations cause common cancers including breast, ovarian, and prostate cancers when heterozygous. Here we report a zebrafish brca2 insertional mutant that shares phenotypes with human patients and identifies a novel brca2 function in oogenesis. Experiments showed that mutant embryos and mutant cells in culture experienced genome instability, as do cells in FA patients. In wild-type zebrafish, meiotic cells expressed brca2; and, unexpectedly, transcripts in oocytes localized asymmetrically to the animal pole. In juvenile brca2 mutants, oocytes failed to progress through meiosis, leading to female-to-male sex reversal. Adult mutants became sterile males due to the meiotic arrest of spermatocytes, which then died by apoptosis, followed by neoplastic proliferation of gonad somatic cells that was similar to neoplasia observed in ageing dead end (dnd-knockdown males, which lack germ cells. The construction of animals doubly mutant for brca2 and the apoptotic gene tp53 (p53 rescued brca2-dependent sex reversal. Double mutants developed oocytes and became sterile females that produced only aberrant embryos and showed elevated risk for invasive ovarian tumors. Oocytes in double-mutant females showed normal localization of brca2 and pou5f1 transcripts to the animal pole and vasa transcripts to the vegetal pole, but had a polarized rather than symmetrical nucleus with the distribution of nucleoli and chromosomes to opposite nuclear poles; this result revealed a novel role for Brca2 in establishing or maintaining oocyte nuclear architecture. Mutating tp53 did not rescue the infertility phenotype in brca2 mutant males, suggesting that brca2 plays an essential role in zebrafish spermatogenesis. Overall, this work verified zebrafish as a model for the role of Brca2 in human disease and uncovered a novel function of Brca2 in vertebrate oocyte nuclear architecture.

Hartree-Fock calculations pertaining to the determination of nuclear binding energies throughout the whole chart of nuclides are reviewed. Such an approach is compared with other methods. Main techniques in use are shortly presented. Advantages and drawbacks of these calculations are also discussed with a special emphasis on the extrapolation towards nuclei far from the stability valley. Finally, a discussion of some selected results from light to superheavy nuclei, is given.

Hartree-Fock calculations pertaining to the determination of nuclear binding energies throughout the whole chart of nuclides are reviewed. Such an approach is compared with other methods. Main techniques in use are shortly presented. Advantages and drawbacks of these calculations are also discussed with a special emphasis on the extrapolation towards nuclei far from the stability valley. Finally, a discussion of some selected results from light to superheavy nuclei, is given [fr

Because of their extended conjugated bond network, aromatic compounds generally have higher redox stability than less saturated compounds. We conjectured that ionic liquids (ILs) consisting of aromatic heterocyclic anions (AHAs) may exhibit improved radiation and electrochemical stability. Such properties are important in applications of these ILs as diluents in radionuclide separations and electrolytes in the electric energy storage devices. In this study, we systematically examine the redox chemistry of the AHAs. Three classes of these anions have been studied: (i) simple 5-atom ring AHAs, such as the pyrazolide and triazolides, (ii) AHAs containing an adjacent benzene ring, and (iii) AHAs containing electron-withdrawing groups that were introduced to reduce their basicity and interaction with metal ions. It is shown that fragmentation in the reduced and oxidized states of these AHAs does not generally occur, and the two main products, respectively, are the H atom adduct and the imidyl radical. The latter species occurs either as an N σ-radical or as an N π-radical, depending on the length of the N-N bond, and the state that is stabilized in the solid matrix is frequently different from that having the lowest energy in the gas phase. In some instances, the formation of the sandwich π-stack dimer radical anions has been observed. For trifluoromethylated anions, H adduct formation did not occur; instead, there was facile loss of fluoride from their fluorinated groups. The latter can be problematic in nuclear separations, but beneficial in batteries. Overall, our study suggests that AHA-based ILs are viable candidates for use as radiation-exposed diluents and electrolytes.

Since the 2011 Fukushima Daiichi nuclear power plant accident, the negative opinion to nuclear power plant has increased and the political debates over the pros and cons of nuclear energy has been activated. This paper attempts to reveal empirically the social determinants of attitudes towards nuclear energy. We focus on generation, gender, and social stratification as the determinants, and examine for the value mediated mechanism. Previous researches have indicated that women tend to have ne...

This Special Analysis for Components-in-Grout (CIG) expands the list of isotopes to the full suite of normal isotopes. This revision also addresses selected isotopes in special waste forms from the K and L basin resin that have waste-specific Kds and high-concentration I-129 wastes with waste-specific Kds, including Effluent Treatment Facility (ETF) activated carbon vessels. The full suite of normal isotopes was first screened using the Slit Trench screening results as a conservative approach. The isotopes that survived the screening were analyzed to determine the appropriate CIG inventory limits. The groundwater modeling was revised to incorporate improvements and changes in other recent Special Analyses and Unreviewed Disposal Question (UDQ) evaluations. The air pathway analysis was modified to consider a distributed source rather than a point source. These changes are discussed below in intruder and groundwater sections. Tables and figures are provided in appendices that are directly related to the most recent analyses. Changes to inventory limits are shown in Table 7. Inventory limits for solubility- limited radionuclides require special treatment as discussed in Section 3.1.1.3. U-238 and Pu-239 were analyzed as being solubility-limited, because otherwise they would consume excessive amounts of their inventory limits. Other U and Pu isotopes were not analyzed as being solubility- limited because they would not consume excessive amounts of inventory limits. Current and projected inventories for the K and L basin resins are compared against inventory limits for a single set of 5 CIG trenches. Projections for the K and L basin waste are through 2035, thus actual inventory consumption is dependent on the total number of CIG trenches excavated and filled through 2035. Current inventory for three ETF activated carbon vessels awaiting disposal are compared against inventory limits for a single set of 5 CIG trenches.

After the publication of the Radiological Hazard Basic Directive, Generalitat (the regional government in Valencian Community) initiated the edition of the pertinent Special Plan, with the objective to assemble the response of all the Security and Emergency Agencies, including the Armed Forces, in a radiological emergency affecting the territory of the Valencian Community, under a single hierarchy command. Being approved and homologated the Radiological Hazard Special Plan, Generalitat has undertaken the implementation process planned to finish in June 2015. Following the same process as other Plans, implementation is organized in a first informative stage, followed of a formative and training stage, and finishing with an activation exercise of the Plan. At the end of the process, is expected that every Agency will know their functions, the structure and organization in which the intervention takes place, the resources needed, and adapt their protocols to the Plan requirements. From the beginning, it has been essential working together with the Nuclear Safety Council, as is established in the agreement signed in order to collaborate in Planning, Preparedness and Response in Radiological Emergencies. [Spanish] Tras la publicación de la Directriz Básica de Riesgo Radiológico, la Generalitat inició la redacción del correspondiente Plan Especial, con el objetivo de articular la respuesta de todos los organismos de Seguridad y Emergencias, y las Fuerzas Armadas, en una emergencia radiológica que afecte al territorio de la Comunidad Valenciana, bajo la dirección de un mando único. Aprobado y homologado el Plan Especial ante el Riesgo Radiológico, la Generalitat ha acometido el proceso de implantación que finalizará en junio de 2015. Por analogía con otros planes de la Comunidad, la implantación se estructura en una primera fase divulgativa e informativa, seguida de una fase formativa y de adiestramiento, culminando con un simulacro de activación del Plan

Dehydrated carrot pomace was assessed for the feasibility of incorporating into baked product by partial substitution of refined flour at 4, 8, and 12% level. As carrot pomace is a good source of antioxidant components and dietary fiber, especially soluble fiber, it was added to the cookies. Carrot pomace and products were analyzed for chemical composition, and products were further evaluated for sensory quality, carotene retention and bioaccessibility, and storage stability. The results show...

The role of the legal instruments in the war against nuclear terrorism. Control of radioactive sources. Elements of Nuclear Law: Definition: it is the body of special legislation that regulates the pacific uses of nuclear energy and the conduct of the persons engaged in activities related to fissionable materials and ionizing radiation . Objective: to provide a legal framework in order to protect individuals , property and the environment against the harmful effects of the use of nuclear energy and ionising radiation. Principles of nuclear energy legislation: safety principle, exclusively operator responsibility, authorization, independence of the regulatory body, inspections and enforcement, nuclear damage compensation, international cooperation. National regulatory infrastructure. Establishment of special law in Emergency Preparedness for nuclear or radiological disaster. IAEA Conventions. Transportation of nuclear material. IAEA regulations on radioactive material. Compensation for nuclear damage. Nuclear safety, security and terrorism. International and domestic instruments. Anti terrorism acts. International agreements on Safety Cooperation. (Author)

Mammalian DNA polymerase {delta} (pol {delta}) is essential for DNA replication, though the functions of this smallest subunit of POLD4 have been elusive. We investigated pol {delta} activities in vitro and found that it was less active in the absence of POLD4, irrespective of the presence of the accessory protein PCNA. shRNA-mediated reduction of POLD4 resulted in a marked decrease in colony formation activity by Calu6, ACC-LC-319, and PC-10 cells. We also found that POLD4 reduction was associated with an increased population of karyomere-like cells, which may be an indication of DNA replication stress and/or DNA damage. The karyomere-like cells retained an ability to progress through the cell cycle, suggesting that POLD4 reduction induces modest genomic instability, while allowing cells to grow until DNA damage reaches an intolerant level. Our results indicate that POLD4 is required for the in vitro pol {delta} activity, and that it functions in cell proliferation and maintenance of genomic stability of human cells.

Mammalian DNA polymerase δ (pol δ) is essential for DNA replication, though the functions of this smallest subunit of POLD4 have been elusive. We investigated pol δ activities in vitro and found that it was less active in the absence of POLD4, irrespective of the presence of the accessory protein PCNA. shRNA-mediated reduction of POLD4 resulted in a marked decrease in colony formation activity by Calu6, ACC-LC-319, and PC-10 cells. We also found that POLD4 reduction was associated with an increased population of karyomere-like cells, which may be an indication of DNA replication stress and/or DNA damage. The karyomere-like cells retained an ability to progress through the cell cycle, suggesting that POLD4 reduction induces modest genomic instability, while allowing cells to grow until DNA damage reaches an intolerant level. Our results indicate that POLD4 is required for the in vitro pol δ activity, and that it functions in cell proliferation and maintenance of genomic stability of human cells.

This book presents the principles and techniques of program specialization - a general method to make programs faster (and possibly smaller) when some inputs can be known in advance. As an illustration, it describes the architecture of Tempo, an offline program specializer for C that can also specialize code at runtime, and provides figures for concrete applications in various domains. Technical details address issues related to program analysis precision, value reification, incomplete program specialization, strategies to exploit specialized program, incremental specialization, and data speci

Full Text Available Since the eruption of the Lusi Mud volcano in Sidoarjo, East Java, on May 2006, soil embankment dams have been built to keep hot mud within the ponds. Unfortunately, since the dams were sitting on poor weak ground, land subsidence intensively occurred around the dams. A finite element method (FEM was, then, applied to evaluate the stability of the dams particularly of the dam point P10.D, being considered as the most unstable point over 29 other dam points. Results show that the dam displacements in vertical and horizontal directions were high. The total displacements of the final design were about 1.5 m in both static- and dynamic-state conditions. These modelled data show a similar trend with field measurement data. The dam had only a factor of safety of about 1.1, and the dam might fail through a deep slide mode.

Full Text Available Road segment of Piyungan - Patuk is a part of Yogyakarta - Wonosari highway, fairly dense traversed by vehicles, from bicycles to buses and trucks. This road crosses hilly topography, causing its sides bounded by quite steep slopes or cliffs. Steep slopes and cliffs are potential to create mass movement. Geologic condition of the surrounding area is built of various volcanic lithology such as breccia, siltstone, sandstone and tuff. There are also geologic structures of joints and faults that affect the stability of the slopes around this road. Slope stability analysis for road segment of Piyungan – Patuk was conducted by applying Markland method. Laboratory testings were done to determine the mechanical and physical properties of rocks that influence the slope strength. Results of the testings show that cohesion and friction angle of volcanic breccia are c = 20.0441 kg/cm2 and  = 56.38˚; cohesion and friction angle of sandstone are cr = 0.6862 kg/cm2, cp = 4.6037 kg/cm2, r = 26.37˚, and p = 32.79˚; cohesion and friction angle of tuff is cr = 1.677 kg/cm2, cp = 7.5553 kg/cm2, r = 17.85˚, and p = 24.19˚. Based on the analysis, some slopes in the study area are potential to move. The movements can be classified into rock fall, debris fall, and rock slides with the sliding plane categorized as planar and wedge. On the other hand, landslide prone zones in the study area can be divided into: Areas with high vulnerability, Areas with moderate vulnerability, and Areas with low vulnerability. Areas prone to landslide should be managed by a series of measures, among others understand natural phenomena, recognizing symptoms of avalanche, attempting to reduce the risk, and land use regulation. The management activities should involve all stakeholders in an integrated manner of implementation.

Written from the basis of neutrality, neither for nor against nuclear power this book considers whether there are special features of nuclear power which mean that its development should be either promoted or restrained by the State. The author makes it dear that there are no easy answers to the questions raised by the intervention of nuclear power but calls for openness in the nuclear decision making process. First, the need for energy is considered; most people agree that energy is the power to progress. Then the historicalzed background to the current position of nuclear power is given. Further chapters consider the fuel cycle, environmental impacts including carbon dioxide emission and the greenhouse effect, the costs, safety and risks and waste disposal. No conclusion either for or against nuclear power is made. The various shades of opinion are outlined and the arguments presented so that readers can come to their own conclusions. (UK)

This chapter of the final report of the Royal Commission on Electric Power Planning in Ontario updates its interim report on nuclear power in Ontario (1978) in the light of the Three Mile Island accident and presents the commission's general conclusions and recommendations relating to nuclear power. The risks of nuclear power, reactor safety with special reference to Three Mile Island and incidents at the Bruce generating station, the environmental effects of uranium mining and milling, waste management, nuclear power economics, uranium supplies, socio-political issues, and the regulation of nuclear power are discussed. Specific recommendations are made concerning the organization and public control of Ontario Hydro, but the commission concluded that nuclear power is acceptable in Ontario as long as satisfactory progress is made in the disposal of uranium mill tailings and spent fuel wastes. (LL)

Nuclear forces play a decisive role to account for the evolution of the nuclear structure and to fix the limits of particle stability. The study of neutron-rich nuclei is particularly important to determine these limits and to reveal the disappearance or emergence of new shell gaps far from stability. We studied the weakly bound neutron-rich 26 F in order to probe the πd 5/2 xνd 3/2 interaction. Indeed this nucleus can be modeled as a closed core of 24 O on top of which a single deeply bound proton in πd 5/2 interacts with an unbound neutron in νd 3/2 . This coupling gives rise to the quadruplet of states J = 1, 2, 3, 4 of positive parity. Their determination would allow us to quantify the intensity of the πd 5/2 xνd 3/2 interaction. Among these states, the J = 1 (ground state) and J = 2 (first excited state) were already known. The search for the J = 4 state has been investigated by our group at GANIL through a β-decay experiment. The nuclei of 26 F were produced by the fragmentation of a 36 S beam and selected using the LISE spectrometer. They were then implanted in a Double Sided Stripped Silicon Detector that gave us the opportunity to achieve spatial and time correlations between the implanted ions and the products of the decays (β and γ rays). Moreover we were able to observe the delayed M3 γ transition from the isomeric J = 4 state to the J = 1 ground state and thus obtained the excitation energy of 643.4 keV for this isomeric state. We also determined several new states in 25-26 Ne that were fed by the β-decay of the ground and isomeric state of 26 F. We extracted an isomeric ratio of about 40% and adjusted the previously determined mass of 26 F according to this value, leading to ΔM = 270 (50) keV. The J = 3 state has been populated ad studied at GSI by means of a one proton knock-out reaction from a radioactive 27 Ne beam to produce the 26 F in its unbound states. When the 26 F is produced in its unbound state J = 3, it decays in 25 F + n. The

A description of the constitutive elements of insurance and its features in the field of law, and special legislation about the matter are given. The relationship between the liability of the nuclear power plant operator and the international conventions about civil liability on nuclear damage is discussed. Some considerations on damage reparing in the United States, Germany, France and Spain are presented. (A.L.S.L.) [pt

Full Text Available Dehydrated carrot pomace was assessed for the feasibility of incorporating into baked product by partial substitution of refined flour at 4, 8, and 12% level. As carrot pomace is a good source of antioxidant components and dietary fiber, especially soluble fiber, it was added to the cookies. Carrot pomace and products were analyzed for chemical composition, and products were further evaluated for sensory quality, carotene retention and bioaccessibility, and storage stability. The results showed that pomace contained protein, (6.50%; dietary fiber (44.75%; total carotene, (5,456 μg; and β-carotene (607 μg/100 g. Products with 4% pomace incorporation had highest retention in terms of total carotene (75% and β-carotene (69%. The highest level of replacement (12% had a significant adverse effect on the product. Overall acceptability indicated that panel members liked the products up to 8% of added carrot pomace compared to control. Thus, it can be stated that value-added cookies could be advantageous as they are nutrient dense containing dietary fiber and carotenoids.

In a strange turn of history, the threat of global nuclear war has gone down, but the risk of a nuclear attack has gone up. The danger of nuclear terrorism and ways to thwart it, tackle it and manage it in the event of an attack is increasingly gaining the attention of nuclear analysts all over the world. There is rising awareness among nuclear experts to develop mechanisms to prevent, deter and deal with the threat of nuclear terrorism. Nuclear specialists are seeking to develop and improve the science of nuclear forensics so as to provide faster analysis during a crisis. Nuclear forensics can play an important role in detecting illicit nuclear materials to counter trafficking in nuclear and radiological materials. An effective nuclear forensic and attribution strategy can enable policy makers, decision makers and technical managers to respond to situations involving interception of specialnuclear materials

Project W-460, Plutonium Stabilization and Handling, encompasses procurement and installation of a Stabilization and Packaging System (SPS) to oxidize and package for long term storage remaining plutonium-bearing specialnuclear materials currently in inventory at the Plutonium Finishing Plant (PFP), and modification of vault equipment to allow storage of resulting packages of stabilized SNM for up to fifty years. This Conceptual Design Report (CDR) provides conceptual design details for the vault modification, site preparation and site interface with the purchased SPS. Two concepts are described for vault configuration; acceleration of this phase of the project did not allow completion of analysis which would clearly identify a preferred approach.

of design patterns. In this paper, we analyze the specialization opportunities provided by specific uses of design patterns. Based on the analysis of each design pattern, we define the associated specialization pattern. These specialization opportunities can be declared using the specialization classes......Design patterns offer many advantages for software development, but can introduce inefficiency into the final program. Program specialization can eliminate such overheads, but is most effective when targeted by the user to specific bottlenecks. Consequently, we propose that these concepts...... are complementary. Program specialization can optimize programs written using design patterns, and design patterns provide information about the program structure that can guide specialization. Concretely, we propose specialization patterns, which describe how to apply program specialization to optimize uses...

Design patterns offer many advantages for software development, but can introduce inefficiency into the final program. Program specialization can eliminate such overheads, but is most effective when targeted by the user to specific bottlenecks. Consequently, we propose that these concepts...... are complementary. Program specialization can optimize programs written using design patterns, and design patterns provide information about the program structure that can guide specialization. Concretely, we propose specialization patterns, which describe how to apply program specialization to optimize uses...... of design patterns. In this paper, we analyze the specialization opportunities provided by specific uses of design patterns. Based on the analysis of each design pattern, we define the associated specialization pattern. These specialization opportunities can be declared using the specialization classes...

A series of mishaps in a reactor at the Three Mile Island (TMI) nuclear plant led to the 1979 meltdown of almost half the uranium fuel and uncontrolled releases of radiation into the air and surrounding Susquehanna River. It was the single worst disaster ever to befall the U.S. nuclear power industry. Health physics technician Randall Thompson's story about what he witnessed while monitoring radiation there after the incident is being publicly disclosed for the first time. It is supported by a growing body of evidence and it contradicts the U.S. government's contention that the TMI accident posed no threat to the public. Thompson and his wife, a nuclear health physicist who also worked at TMI in the disaster's wake, warn that the government's failure to acknowledge the full scope of the disaster is leading officials to underestimate the risks posed by a new generation of nuclear power plants.

A long and intense effort to stabilize and repackage nearly 18 metric tons (MT) of plutonium-bearing leftovers from defense production and nuclear experiments concluded successfully in February, bringing universal congratulations to the Department of Energy's Hanford Site in southeast Washington State. The victorious stabilization and packaging endeavor at the Plutonium Finishing Plant (PFP), managed and operated by prime contractor Fluor Hanford, Inc., finished ahead of all milestones in Hanford's cleanup agreement with regulators, and before deadlines set by the Defense Nuclear Facilities Safety Board (DNFSB), a part of the federal Executive Branch that oversees specialnuclear materials. The PFP stabilization and packaging project also completed under budget for its four-year tenure, and has been nominated for a DOE Secretarial Award. It won the Project of the Year Award in the local chapter competition of the Project Management Institute, and is being considered for awards at the regional and national level

A first set of articles addresses the nuclear crisis in Japan (description of the accident, information mission sent by France, and support actions undertaken by France in Japan in the fields of education, civilian security, culture, sailing, media, dosimeters, robotics). A second set discusses lessons learned in terms of nuclear safety (complementary safety assessments, stress test in Gravelines), radiological consequences (impact on Japanese population, the Symbiose software, the Teleray network), crisis management, and research

Copper is a stable element and spent fuel component which constitutes the radioactive waste. The reaction of Copper with cellulose degradation products in alkaline conditions was performed to mimic what occurs in near field conditions of nuclear waste repository. From the characteristics of Cu (II), this thesis aims at inferring the behaviour of radionuclides vis a vis the degradation products of cellulose. The contribution of the present work is therefore the assessment of the stability of the major cellulose degradation product, its affinity for Copper and the extent of the complexation function 13 between Cu (II) and the organic moieties. The formation of cellulose degradation products was followed by measurement of p11, Conductivity, Angle of rotation, relative abundance of aliphatics and aromatics (E4/E6 ) aid by UV-visible spectroscopy. The TOC was determined using the Walkley and Black titration after respectively 31 weeks and 13 weeks of degradation for the reaction mixtures T and A, N. The stability of the major degradation products gave the following figures: ISA(A): - 13 43.39

The thermal stability of the French nuclear waste glass was investigated experimentally and by modeling to predict its long-term evolution at low temperature. The crystallization mechanisms were analyzed by studying devitrification in the supercooled liquid. Three main crystalline phases were characterized (CaMoO{sub 4}, CeCO{sub 2}, ZnCr{sub 2}O{sub 4}). Their crystallisation was TO 4.24 wt%, due to the low concentration of the constituent elements. The nucleation and growth curves showed that platinoid elements catalysed nucleation but did not affect growth, which was governed by volume diffusion. The criteria of classic nucleation theory were applied to determine the thermodynamic and diffusional activation energies. Viscosity measurements illustrate the analogy between the activation energy of viscous flow and diffusion, indicating control of crystallization by viscous flow phenomena. The combined action of nucleation and growth was assessed by TTT plots, revealing a crystallization equilibrium line that enables the crystallized fractions to be predicted over the long term. The authors show that hetero-genetics catalyze the transformation without modifying the maximum crystallized fraction. A kinetic model was developed to describe devitrification in the glass based on the nucleation and growth curves alone. The authors show that the low-temperature growth exhibits scale behavior (between time and temperature) similar to thermo-rheological simplicity. The analogy between the resulting activation energy and that of the viscosity was used to model growth on the basis of viscosity. After validation with a simplified (BaO{sub 2}SiO{sub 2}) glass, the model was applied to the containment glass. The result indicated that the glass remained completely vitreous after a cooling scenario with the one measured at the glass core. Under isothermal conditions, several million years would be required to reach the maximum theoretical crystallization fraction. (author)

Two possible patterns of proliferation appear to involve the greatest risks for nuclear use or war. The first is proliferation to particular categories of states and the second dangerous possibility is proliferation at a rapid rate. But rapid proliferation could cause instabilities that might be too great for political systems and institutions to handle, making nuclear use of nuclear war more likely. Thus, any strategy for nonproliferation should especially attempt to prevent a rapid spread of nuclear weapons and to avert acquisition by states in the high-risk categories. Nuclear proliferation will also have important effects on world and regional stability for reasons not directly related to nuclear use. The mere possession of nuclear weapons by certain states could radically alter international perceptions and threaten global arrangements. The main concern in this discussion is to analyze the various incentives and disincentives--involving both security and political considerations--that will affect states' decisions about whether or not to acquire nuclear weapons. The discussion then turns to the means by which individual states and the international community can influence nuclear incentives and disincentives. The particularly important subject of the management of the international nuclear industry is addressed separately, followed by an analysis of nuclear acquisition, use, and threat by non-state entities. Finally, a general strategy for decreasing incentives and increasing disincentives is proposed and applied to four special categories of states

The paper starts with a general survey of post-Cold War nuclear disarmament, pointing out Japan's positions, policies, and problems in the process. The discussion is not Japan-centered, nor is it an explanation of the Japanese view. It is useful, in this context, to recall that during the Cold War period, Japan was firmly in the ''Western Camp'', relying on the protection of the extended nuclear deterrence provided by the United States. This article is written with that history very much in mind, and by an author who for some years was in a position to represent Japan in such a context. (orig./DG)

to life at high temperatures so are their enzymes, as a result the high stability is accompanied by low activity at moderate temperatures. Thus, much effort had been put into decoding the mechanisms behind the high stability of the thermophilic enzymes. The hope is to enable scientist to design enzymes...... in the high stability of hyperthermophilic enzymes. The thesis starts with an introduction to the field of protein and enzyme stability with special focus on the thermophilic and hyperthermophilic enzymes and proteins. After the introduction three original research manuscripts present the experimental data...

Concrete is the most convenient material when large-scale radiation protection is needed. Thus, special concretes for nuclear purposes are used in various facilities like reactors, reprocessing centers, storage sites, accelerators, hospitals with nuclear medicine equipment, food ionization centers etc.. The recent advances made in civil engineering for the improvement of concrete durability and compactness are for a large part transposable to protection concretes. This article presents the basic knowledge about protection concretes with the associated typological and technological aspects. A large part is devoted to the intrinsic properties of concretes and to their behaviour in irradiation and temperature conditions: 1 - definition and field of application of special protective concretes; 2 - evolution of concepts and technologies (durability of structures, techniques of formulation, new additives, market evolution); 3 - design of protective structures (preliminary study, radiation characteristics, thermal constraints, damping and dimensioning, mechanical criteria); 4 - formulation of special concretes (general principles, granulates, hydraulic binders, pulverulent additives, water/cement ratio, reference composition of some special concretes); 5 - properties of special concretes (damping and thermo-mechanical properties); 6 - induced-irradiation and temperature phenomena (activation, radiolysis, mineralogical transformations, drying, shrinking, creep, corrosion of reinforcement). (J.S.)

The first step of on-the-job training is practical observation phase in an operating Nuclear Plant, where the participants are assigned to shift work. The simulator training for operating personnel, for key personnel and, to some extent, also for maintenance personnel and specialists give the practical feeling for Nuclear Power Plant behaviour during normal and abnormal conditions. During the commissioning phase of the own Nuclear Power Plant, which is the most important practical training, the participants are integrated into the commissioning staff and assisted during their process of practical learning by special instructors. The preparation for the licensing exams is vitally important for shift personnel and special courses are provided after the first non-nuclear trial operation of the plant. Personnel training also includes performance of programmes and material for retraining, training of instructors and assistance in building up special training programmes and material as well as training centers. (orig./RW)

Total nuclear power generation in Germany in 1999 sums up to 169.7 billion kWh and thus almost equals the all-time high of the operating year 1997, which was at 170.4 billion kWh. Power generation in nuclear power plants has been contributing well a third of the total domestic power supply since 1988, which is about ten per cent of the national power consumption. This is one aspect of the information contained in the annual report of Deutsches Atomforum e.V. Expressing this 1999 output in terms of carbon dioxide emissions avoided, the figure is 170 million tonnes. This is equal to the annual CO2 emissions in 1999 emanating from road transport and traffic in Germany. From the very beginning of nuclear power generation in 1961 until today, aggregated nuclear power generation from uranium and plutonium fuels amounts to about 2.8 billion kWh, which means that over this period, more than two billion tonnes of carbon dioxide emissions have been avoided. (orig./CB) [de

A very wide variety of sample preparation is used in the Special Training Division's research and teaching programmes. These range from simple source holders such as metal, cardboard and plastic source mounts, to precipitation devices using stainless steel and fibreglass mounts, and special source holders for liquid counting of samples. In addition to these techniques, a number of procedures of special interest in biomedical problems have been developed. One of the most important of these is the use of a catalytic synthesis of benzene which has been developed to the point to which an over-all yield of better than 90% is obtained. This synthesis can be used for carbon-containing compounds of interest in low-level tracing experiments and age dating problems. Since the synthesis involves the production of carbon dioxide at one step and the hydration of metallic carbide in another, it can be used either for the measurement of 14 C or 3 H or both in double labelling experiments. Considerable work is done on activation analysis of biological materials, particularly in the Division's radioecological programmes. Special techniques for the preparation of these materials for activation analysis and other radiochemical procedures are described. Since the problem of resolution in alpha-ray spectroscopy remains a very difficult one, considerable work is carried out by the oceanography and environmental studies group in the development of very thin samples which are capable of permitting higher resolution of alpha-ray spectra. These employ electrodeposition procedures from mixed solvents. Measurements are made with a special bank of Fairstein-Frisch grid counters associated with a 512-channel analyser for simultaneous recording of more than one spectrum. Solid-state detectors are also used and comparative results of gridded and solid-state detectors are shown. (author) [fr

In this work author proposes to constitute new virtual library which should centralize the information from nuclear disciplines on the INTERNET, in order to them to give first and foremost the connection on the most important links in set nuclear sciences. The author has entitled this new virtual library The World Wide Web Library: Nuclear Sciences. By constitution of this virtual library next basic principles were chosen: home pages of international organizations important from point of view of nuclear disciplines; home pages of the National Nuclear Commissions and governments; home pages of nuclear scientific societies; web-pages specialized on nuclear problematic, in general; periodical tables of elements and isotopes; web-pages aimed on Chernobyl crash and consequences; web-pages with antinuclear aim. Now continue the links grouped on web-pages according to single nuclear areas: nuclear arsenals; nuclear astrophysics; nuclear aspects of biology (radiobiology); nuclear chemistry; nuclear company; nuclear data centres; nuclear energy; nuclear energy, environmental aspects of (radioecology); nuclear energy info centres; nuclear engineering; nuclear industries; nuclear magnetic resonance; nuclear material monitoring; nuclear medicine and radiology; nuclear physics; nuclear power (plants); nuclear reactors; nuclear risk; nuclear technologies and defence; nuclear testing; nuclear tourism; nuclear wastes; nuclear wastes. In these single groups web-links will be concentrated into following groups: virtual libraries and specialized servers; science; nuclear societies; nuclear departments of the academic institutes; nuclear research institutes and laboratories; centres, info links

This report discusses the links between safety assessment and environmental impact assessment as applied to operations for unloading of spent nuclear fuel from the Lepse storage vessel. Regulatory responsibilities and regulatory requirements in these areas are under discussion and development in the Russian Federation and in other countries. The authors provide a briefing, based on inputs from Russian and western organisations, of their understanding of the situation at the time the work was done. They also make a variety of suggestions according to their perspectives. These suggestions should be relevant to the Lepse situation and to some other nuclear activities, bur do not represent the position of any particular organisation. Accordingly, this report is published by the SSI with the intention to promote discussion and interaction among relevant authorities

This report discusses the links between safety assessment and environmental impact assessment as applied to operations for unloading of spent nuclear fuel from the Lepse storage vessel. Regulatory responsibilities and regulatory requirements in these areas are under discussion and development in the Russian Federation and in other countries. The authors provide a briefing, based on inputs from Russian and western organisations, of their understanding of the situation at the time the work was done. They also make a variety of suggestions according to their perspectives. These suggestions should be relevant to the Lepse situation and to some other nuclear activities, bur do not represent the position of any particular organisation. Accordingly, this report is published by the SSI with the intention to promote discussion and interaction among relevant authorities.

In particular for older German nuclear power plants there are projects to modernize I and C and process information systems. This modernization mainly aims at improvements in plant operation. For instance, using modern computing technology, the plant operation can be optimized, according to further details. Furthermore, the problem of spare-part keeping for out-dated components can be solved. For modernizing the I and C or the process computer system, safety-relevant aspects have to be taken into account. For instance, the compatibility of the system modification with the existing alarm annunciation concept shall be considered, and for each modernization step, the interfaces between the equipment of different safety significance shall be assessed and observed. The functions and the associated equipment have to be qualified in accordance to their safety significance. At present, the regulatory framework for computer-based instrumentation and control as well as for information systems is being elaborated in Germany and worldwide. Recently, the guidelines of the German Reactor Safety Commission have been extended with regard to the introduction and safety application of modern computer-based I and C in nuclear power plants. Furthermore, some of the essential requirements for design and qualification of modern I and C can be derived from the existing rules and standards. Particularly, concerning the alarm annunciation system, this report summarizes safety-relevant aspects of the modernization of the instrumentation and control system as well as the process information system in nuclear power plants. (author). 4 refs

Beside new Ordinance on the control of nuclear material and special equipment ('Official Gazette' No. 15/08), from 2006 State Office for Nuclear Safety (SONS) adopted Ordinance on performing nuclear activities ('Official Gazette' No. 74/06) and Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety ('Official Gazette' No. 74/06), based on Nuclear Safety Act ('Official Gazette' No. 173/03). The Ordinance on performing nuclear activities regulates the procedure of notification of the intent to perform nuclear activities, submitting the application for the issue of a licence to perform nuclear activities, and the procedure for issuing decisions on granting a licence to perform a nuclear activity. The Ordinance also regulates the content of the forms for notification of the intent to perform nuclear activities, as well as of the application for the issue of a licence to perform the nuclear activity and the method of keeping the register of nuclear activities. According to the Nuclear Safety Act, nuclear activities are the production, processing, use, storage, disposal, transport, import, export, possession or other handling of nuclear material or specified equipment. The Ordinance on special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety regulates these mentioned conditions, whereas compliance is established by a decision passed by the SONS. Special requirements which expert organizations must fulfil in order to perform certain activities in the field of nuclear safety are organizational, technical, technological conditions and established system of quality assurance. In 2007, State Office for Nuclear Safety finalized the text of new Ordinance on conditions for nuclear safety and protection with regard to the siting, design, construction, use and decommissioning of a facility in which a nuclear activity is

This paper analyses the historical aspects of the nuclear right development. It makes the evolution of the fundamental principles of nuclear right, in special, the civil responsibility for nuclear damages. (author)

The collection of abstracts on selected topics in nuclear structure are given. Special attention pays to collective excitations and high-spin states of nuclei, giant resonance structure, nuclear reaction mechanisms and so on

As the body of scientific knowledge in a discipline increases, there is pressure for specialization. Fields spawn subfields that then become entities in themselves that promote further specialization. The process by which scientists join specialized groups has remarkable similarities to the guild system of the middle ages. The advantages of specialization of science include efficiency, the establishment of normative standards, and the potential for greater rigor in experimental research. However, specialization also carries risks of monopoly, monotony, and isolation. The current tendency to judge scientific work by the impact factor of the journal in which it is published may have roots in overspecialization, as scientists are less able to critically evaluate work outside their field than before. Scientists in particular define themselves through group identity and adopt practices that conform to the expectations and dynamics of such groups. As part of our continuing analysis of issues confronting contemporary science, we analyze the emergence and consequences of specialization in science, with a particular emphasis on microbiology, a field highly vulnerable to balkanization along microbial phylogenetic boundaries, and suggest that specialization carries significant costs. We propose measures to mitigate the detrimental effects of scientific specialism.

A special manifold is an allowed target manifold for the vector multiplets of D=4, N=2 supergravity. These manifolds are of interest for string theory because the moduli spaces of Calabi-Yau threefolds and c=9, (2,2) conformal field theories are special. Previous work has given a local, coordinate-dependent characterization of special geometry. A global description of special geometries is given herein, and their properties are studied. A special manifold M of complex dimension n is characterized by the existence of a holomorphic Sp(2n+2,R)xGL(1,C) vector bundle over M with a nowhere-vanishing holomorphic section Ω. The Kaehler potential on M is the logarithm of the Sp(2n+2,R) invariant norm of Ω. (orig.)

The subject is discussed, with special reference to the United Kingdom, under the headings: the need for nuclear power; Britain's experience (nuclear reactors); the nuclear process; how fuel is made; recycling fuel; wastes and their treatment; decommissioning; fast reactors; nuclear fusion; safety and radiation. (U.K.)

The LPAD (French Atomic Energy Commission) develops innovative processes in the frame of the future dismantling of nuclear facilities. Formulations were developed using high viscosified foams stabilized by biodegradable nonionic surfactants: alkyl poly-glucosides and viscosifiers (xanthan gum), which allow us to increase the foam lifetime and thus contact time of chemical reactants with the facility walls. We have considered the relationships between physicochemical properties and foam stability through the exploration of the foam at three different scales: from the molecular range (micelles, surface tension and visco-elasticity), to the film and Plateau border range (XR reflectivity, surface shear viscosity) and to macroscopic range, meaning the whole foam (foaminess, liquid fraction and wall film thickness evolution). Finally, exploratory study is presented concerning simultaneous foam three scales characterisation by small angle neutron scattering. (author)

This report provides a summary of progress for the project ``Evaluation of the Geologic Relations and Seismotectonic Stability of the Yucca Mountain Area, Nevada Nuclear Waste Site Investigation (NNWSI)`` for the eighteen month period of January 1, 1987 to June 10, 1988. This final report was preceded by the final report for the initial six month period, July 1, 1986 to December 31, 1986 (submitted on January 25, 1987, and revised in June 1987.) Quaternary Tectonics, Geochemical, Mineral Deposits, Vulcanic Geology, Seismology, Tectonics, Neotectonics, Remote Sensing, Geotechnical Assessments, Geotechnical Rock Mass Assessments, Basinal Studies, and Strong Ground Motion.

The report is the seventh report in a series of annual reports on the international development of nuclear power production, with special emphasis on safety issues and nuclear emergency preparedness. The report is written in collaboration between Risoe DTU and the Danish Emergency Management Agency. The report for 2009 covers the following topics: status of nuclear power production, regional trends, reactor development, safety related events, international relations, conflicts and the European safety directive. (LN)

-disciplinarily, because they work with both derivative and contributory approaches. Derivative, because specialized language retrieves its philosophy of science as well as methods from both the natural sciences, social sciences and humanistic sciences. Contributory because language results support the communication...... science fields communicate their findings. With this article, we want to create awareness of the work in this special area of language studies and of the inherent cross-disciplinarity that makes LSP special compared to common-core language. An acknowledgement of the importance of this field both in terms...

High-energy resolution diode type CdTe detectors were fabricated by growing an n-type epitaxial layer on high resistivity p-like crystal wafers, and their stability issues during a long-term operation were studied. Room temperature stability of the detectors was not good at low operating biases of around 200 V. However, it could be improved significantly by operating them at higher biases under full depletion conditions. On the other hand, detectors exhibited excellent stability by cooling them slightly below room temperature down to 0 deg. C. The effect of this low level of cooling on detector stability was found to be more significant than that of applying high biases at room temperature. By using the detector type presented here, stable operation could be obtained at moderate operating voltages of around 400 V and with a modest degree of cooling.

The objective of this research was to study the long-term performance of structures comprising nuclear power plants. The time period of interest for this study is 140 years (this figure is based on maximum periods of 40 years for operation and 100 years of storage). It was divided in two parts: - the first based on four UK nuclear power plants examine the principle deterioration mechanism of reinforced structure which is chloride ingress and carbonation penetration - the second based on 2 German nuclear power plants examine the long term behaviour of reinforced and prestressed concrete and also the corrosion of steel containments with particular reference on plastic seals and potential risk areas

The present paper investigated the enhancement of moisture-separation efficiency for ordinary special crossunder pipe separators (SCRUPSs) and proposed three structure-modified separators (combined separator, Z-shaped SCRUPSs, and spiral-type SCRUPSs). Deposition mechanisms for droplets with different sizes were considered using commercial CFD flow solver. Results show that three structure modified separators can increase droplet deposition rate to varying degrees. Regarding flow losses, spiral-type SCRUPSs cause the highest increase, with a total pressure loss coefficient of 231%, although it has the best deposition rate improvement. Among the three structure-modified separators, 'Z' shape separator has the best separation performance because of its higher moisture-separation efficiency and lower total pressure loss efficiency. Results could provide theoretical basis for research on and development of this new type of moisture separator.

Specialized publications such as "Opera News,""Gourmet," and "Forbes" can bring an institution's story to targeted audiences. The experiences of Chautauqua Institution are described. Some of the benefits of marketing articles to these publications are discussed. (MLW)

The current world-wide emphasis on reducing greenhouse gas (GHG) emissions provides an opportunity to revisit how energy is produced and used, consistent with the need for human and economic growth. Both the scale of the problem and the efforts needed for its resolution are extremely large. We argue that GHG reduction strategies must include a greater penetration of electricity into areas, such as transportation, that have been the almost exclusive domain of fossil fuels. An opportunity for electricity to displace fossil fuel use is through electrolytic production of hydrogen. Nuclear power is the only large-scale commercially proven non-carbon electricity generation source, and it must play a key role. As a non-carbon power source, it can also provide the high-capacity base needed to stabilize electricity grids so that they can accommodate other non-carbon sources, namely low-capacity factor renewables such as wind and solar. Electricity can be used directly to power standalone hydrogen production facilities. In the special case of CANDU reactors, the hydrogen streams can be preprocessed to recover the trace concentrations of deuterium that can be re-oxidized to heavy water. World-wide experience shows that nuclear power can achieve high standards of public safety, environmental protection and commercially competitive economics, and must . be an integral part of future energy systems. (author)

GNF Engineering is developing together with ENRESA and with the UNESA participation, the spent fuel and high activity radioactive waste data base of Spanish nuclear power plants. In the article is detailed how this strategic project essential to carry out the CTS (centralized temporary storage) future management and other project which could be emerged is being dealing with, This data base will serve as mechanics of relationship between ENRESA and Spanish NPPS, covering the expected necessary information to deal with mentioned future management of spent fuel and high activity radioactive waste. (Author)

Full Text Available ... can be superimposed with computed tomography (CT) or magnetic resonance imaging (MRI) to produce special views, a ... In contrast, nuclear medicine procedures use a radioactive material, called a radiopharmaceutical or radiotracer, which is injected ...

Full Text Available ... or imaging device that produces pictures and provides molecular information. In many centers, nuclear medicine images can be superimposed with computed tomography (CT) or magnetic resonance imaging (MRI) to produce special views, a practice ...

Full Text Available ... organs and tissues in your body. Hybrid imaging techniques (PET/CT, SPECT/CT and PET/MR) are ... equipment look like? The special camera and imaging techniques used in nuclear medicine include the gamma camera ...

Full Text Available ... nuclear medicine imaging uses small amounts of radioactive materials called radiotracers, a special camera and a computer ... medical imaging that uses small amounts of radioactive material to diagnose and determine the severity of or ...

This paper discusses: the state of computer networking within nuclear physics program; network requirements for nuclear physics; management structure; and issues of special interest to the nuclear physics program office

The seawater piping trench of Fukushima Daiichi Nuclear Power Station connects the screen pump room and turbine building. High concentration contaminated water stagnated in the trench due to the 2011 off the Pacific coast of Tohoku Earthquake, which caused a leakage accident. In order to solve the future leakage risk, a replacement work the liquid with cement was performed to remove contaminated water inside the trench. This paper explains the development of cement filler applied to the trench and the outline of its application work. Long-distance underwater fluid filler that can flow in the water throughout the longest 85 m long shafts was developed and its fluidity was confirmed in a laboratory and mockup device. In the field application, a cement manufacturing plant was set up in the power plant premises, and it took about a year to pour the cement into the trenches of No 2, 3, and 4 Units. To prevent the leakage of contaminated water in the trench, the cement pouring was performed while controlling the water level. Due to the high concentration of contaminated water, workers' radiation exposure management was conducted on a daily and monthly basis, and cumulative radiation exposure was strictly controlled. For radiation shielding, laying crushed stone and iron plate, installation of concrete protection wall and lead wool mat, and use of tungsten vest during work were practiced. Thanks to these measures, it was possible to reduce the exposure dose to about 27% of the originally predicted level. (A.O.)

Repository performance assessment is analysis that identifies events and processes that might affect a repository system for isolation of radioactive waste, examines their effects on barriers to waste migration, and estimates the probabilities of their occurrence and their consequences. In 1983 Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) prepared two plans - one for performance assessment for a waste repository in salt and one for verification and validation of performance assessment technology. At the request of the US Department of Energy's Salt Repository Project Office (SRPO), Argonne National Laboratory reviewed those plans and prepared this report to advise SRPO of specific areas where ONWI's plans for performance assessment might be improved. This report presents a framework for repository performance assessment that clearly identifies the relationships among the disposal problems, the processes underlying the problems, the tools for assessment (computer codes), and the data. In particular, the relationships among important processes and 26 model codes available to ONWI are indicated. A common suggestion for computer code verification and validation is the need for specific and unambiguous documentation of the results of performance assessment activities. A major portion of this report consists of status summaries of 27 model codes indicated as potentially useful by ONWI. The code summaries focus on three main areas: (1) the code's purpose, capabilities, and limitations; (2) status of the elements of documentation and review essential for code verification and validation; and (3) proposed application of the code for performance assessment of salt repository systems. 15 references, 6 figures, 4 tables

This paper focuses on just one essential component of a 'non nuclear' future - the management of nuclear waste. Waste produced by nuclear power is invariably contaminated by radioactivity. It is therefore a serious health and environmental hazard which requires special consideration. As residual radioactive contamination is generally very long lasting, the treatment and disposal options not only have to be robust in themselves, but also capable of retaining their integrity for hundreds, even thousands of years. Until now the debate over the issue of nuclear waste has been polarised; on the one hand there are those who see blocking a long-term solution to waste management as a powerful lever against further nuclear development. On the other, there are those who are in favour of a nuclear-powered future and who consequently have attempted to minimise the problem of dealing with nuclear waste. However, the time is now right for developing a long-term waste strategy for two reasons. Firstly we are confronted with reality, as nuclear plants coming to the end of their life are decommissioned, and secondly, the privatisation of the electricity generation market- has meant that nuclear cannot longer compete in the market with cheaper forms of energy generation and so new build is unlikely. Two options for storing waste have, in the main, been explored: surface storage and geological disposal with the option of retrieval. We believe that geological disposal is the only real option as it does not rely on future societal or climate stability to remain safe and secure. The most vital requirements for the success of finding a long-term solution are public support and legitimacy. Nirex's attempt to gain planning permission for the Rock Characterisation Facility and experience in other countries of gaining support for geological disposal bear this out

This report discusses events and processes that could adversely affect the long-term stability of a nuclear fuel waste disposal vault or the regions of the geosphere and the biosphere to which radionuclides might migrate from such a vault

Repository performance assessment is analysis that identifies events and processes that might affect a repository system for isolation of radioactive waste, examines their effects on barriers to waste migration, and estimates the probabilities of their occurrence and their consequences. In 1983 Battelle Memorial Institute's Office of Nuclear Waste Isolation (ONWI) prepared two plans - one for performance assessment for a waste repository in salt and one for verification and validation of performance assessment technology. At the request of the US Department of Energy's Salt Repository Project Office (SRPO), Argonne National Laboratory reviewed those plans and prepared this report to advise SRPO of specific areas where ONWI's plans for performance assessment might be improved. This report presents a framework for repository performance assessment that clearly identifies the relationships among the disposal problems, the processes underlying the problems, the tools for assessment (computer codes), and the data. In particular, the relationships among important processes and 26 model codes available to ONWI are indicated. A common suggestion for computer code verification and validation is the need for specific and unambiguous documentation of the results of performance assessment activities. A major portion of this report consists of status summaries of 27 model codes indicated as potentially useful by ONWI. The code summaries focus on three main areas: (1) the code's purpose, capabilities, and limitations; (2) status of the elements of documentation and review essential for code verification and validation; and (3) proposed application of the code for performance assessment of salt repository systems. 15 references, 6 figures, 4 tables.

The State System of Accounting for and Control of Nuclear Material (SSAC) is based on requirements resulting from the Safeguards Agreement between the Government of the Slovak Republic and the IAEA. UJD performs this activity according to the 'Atomic Act' and relevant decree. The purpose of the SSAC is also to prevent unauthorised use of nuclear materials, to detect loses of nuclear materials and provide information that could lead to the recovery of missing material. The main part of nuclear materials under jurisdiction of the Slovak Republic is located at NPP Jaslovske Bohunice, NPP Mochovce and at interim storage in Jaslovske Bohunice. Even though that there are located more then 99% of nuclear materials in these nuclear facilities, there are not any significant problems with their accountancy and control due to very simply identification of accountancy units - fuel assemblies, and due to stability of legal subjects responsible for operation and for keeping of information continuity, which is necessary for fulfilling requirements of the Agreement. The nuclear material located outside nuclear facilities is a special category. There are 81 such subjects of different types and orientations on the territory of the Slovak Republic. These subjects use mainly depleted uranium as a shielding and small quantity of natural uranium, low enrichment uranium and thorium for experimental purposes and education. Frequent changes of these subjects, their transformations into the other subjects, extinction and very high fluctuation of employees causes loss of information about nuclear materials and creates problems with fulfilling requirements resulting from the Agreement. In 2001, the UJD carried out 51 inspections of nuclear materials, of which 31 inspections were performed at nuclear installations in co-operation with the IAEA inspectors. No discrepancies concerning the management of nuclear materials were found out during inspections and safeguards goals in year 2001 were

Some aspects of the nuclear activities in Brazil, specially concerning the Goiania s accident are demonstrated using concepts from environmental and nuclear law. Nuclear and environmental competence, the impossibility of the states of making regional laws, as the lack of regulation about the nuclear waste, are discussed. The situation of Goiania when the accident happened, the present situation of the victims and the nuclear waste provisionally stored in Abadia de Goias is reported

This series of slides draws a picture of nuclear engineering training in France. The nuclear sector is very active and developed in France and covers all the aspects of the fuel cycle which implies a strong demand for highly skilled and trained staff. There are both an active involvement of industry in the education process through the design of adequate curricula and a strong support of the State. There are 5 masters dedicated to Science Nuclear Energy (Paris), Nuclear Waste Management (Nantes), Separation Chemistry (Montpellier), Materials for Nuclear Engineering (Grenoble), and 1 engineer degree in nuclear engineering (Saclay). In 2010-2011 there were about 1000 students completing a nuclear energy curriculum (nuclear engineering or specializednuclear domains) at the master-engineer level throughout France. The detailed curriculum of the Master of Science Nuclear Energy is given. The National Institute of Nuclear Sciences and Techniques (INSTN) plays an important role, it has trained a large fraction of the French leading nuclear practitioners through its 50 years old 'Genie Atomique' curriculum. INSTN proposes also high level courses in nuclear disciplines including training of nuclear physicians, radio-pharmacists and medical physicists and is a major player for continuing education in nuclear sciences. (A.C.)

After the successful trial run in 2007, the 2008 GRS Specialized Forum held at the Cologne Wolkenburg on April 7 and 8, 2008 was a full success. GRS, Gesellschaft fuer Anlagen- und Reaktorsicherheit, plans to resume in this way its GRS specialized lectures series with a tradition of many years. Approximately 180 participants from public authorities, licensees, the nuclear industry, research and engineering establishments as well as universities showed their interest in current GRS activities. On 2 days, only GRS experts presented fundamental and GRS-specific approaches in scientific analysis, new research findings, and possibilities of advancing scientific methods under the four headings of Reactor Safety Research and Evaluation, Topical Subjects of Reactor Safety, Radiation Protection Activities, and Repository Safety and Environmental Research. The discussions held after each presentation offered a number of critical, but valuable and welcome, contributions from the different perspectives of the discussants. (orig.)

Includes six special reports: "Libraries and the National Information Infrastructure" (Peter R. Young and Jane Williams); "Library Cooperation and Networking" (JoAn Segal); "Mexican Information Resources in Electronic Format" (Shirley Ainsworth); "The International Role of U.S. Librarians" (Hannelore B.…

The EU has decided to push ahead with biofuels, deflecting criticism with stringent environmental safeguards. In a special section correspondents of the magazine take stock of the ups and downs of the biofuels business. As it turns out, national policies differ widely, leading to a very uneven playing field. Nevertheless, it appears that biofuels have reached the point of no return

Superconductor stability is at the core of the design of any successful cable and magnet application. This chapter reviews the initial understanding of the stability mechanism, and reviews matters of importance for stability such as the nature and magnitude of the perturbation spectrum and the cooling mechanisms. Various stability strategies are studied, providing criteria that depend on the desired design and operating conditions.

The book shows why Britain adopted postwar defence policies that entailed nuclear weapon tests, why more than half of these tests were in Australia, where and how they took place, how the two nations cooperated and what was achieved at what cost. The radiation safety standards of the time and of the present day are compared and the safety aspects of the trials are looked at from the contemporary and present day viewpoint. The book covers the five series of trials in Australia and discusses the very special relationship that existed between the United Kingdom and Australia that made them possible. (author)

After the catastrophic 2011 Tohoku earthquake and tsunami which struck cities and towns on the Japanese Pacific coast, Fukushima has been the focus of special and serious disaster relief procedures modification regarding nuclear power plant accidents. To date, the Japanese government has repeatedly issued evacuation orders to more than 100,000 residents. Huge numbers of refugees are still uncertain if they can return home and re-cultivate their farm land. Ambiguous public announcements concerning the radiation risks seem to have aggravated feelings of insecurity, fear and the desire to escape, both at home and abroad. This disaster has seriously undermined trust internationally and locally in Fukushima. Harmful rumors added further difficulties. In response to this disaster, local government, medical institutions, care facilities, police, emergency services and the self-defense forces continue to put their utmost effort into reconstruction. This seismic disaster has reminded us that supplies of water, electricity, gas, gasoline and telephone communication facilities are essential prerequisites for reconstruction and daily life. Disaster and radiation medical association teams actively participated in the rescue efforts, and a number of organized medical teams cared for about 15,000 refugees in 100 shelters. We also visited homebound patients, who were unable to evacuate from the 20-30 km inner evacuation area. In this relief role, we need to consider the following; (1) professionals, both healthcare and nuclear engineers, must always be prepared for unexpected circumstances, (2) the daily organic cooperation of individuals and units is closely linked to readiness against sudden risks, and (3) appropriate accountability is essential to assuage the fears of residents and refugees. A sincere learning process may benefit those innocent refugees who may be forced to abandon their homes permanently. (author)

Radiation hazards are trans-boundary. The prevention of accidents must be managed locally. But the awareness, preparedness, and the responsibilities in the case of emergencies must be managed at the local and regional level, and must rely on close interaction between the local and regional levels. The Baltic Sea Region contains over 40 nuclear reactors contributing to energy security, but also posing a potential threat to human, environmental, and political security. The aim of this paper is to integrate the four fields of security: health, environment, energy, and political by analysing awareness, preparedness responsibility and decision making related to nuclear installations. With increasing political, economical, cultural and physical (in term of energy infrastructure) integration, the region needs to take a comprehensive approach to create adequate structure for managing risks and thereby promote security. (authors)

Radiation hazards are trans-boundary. The prevention of accidents must be managed locally. But the awareness, preparedness, and the responsibilities in the case of emergencies must be managed at the local and regional level, and must rely on close interaction between the local and regional levels. The Baltic Sea Region contains over 40 nuclear reactors contributing to energy security, but also posing a potential threat to human, environmental, and political security. The aim of this paper is to integrate the four fields of security: health, environment, energy, and political by analysing awareness, preparedness responsibility and decision making related to nuclear installations. With increasing political, economical, cultural and physical (in term of energy infrastructure) integration, the region needs to take a comprehensive approach to create adequate structure for managing risks and thereby promote security. (authors)

Since the beginning of nuclear industry, civil responsibility with damages to the public health and properties was a critical problem, because the special conditions of this industry (nuclear accident, damages could be very high but probability of these events is very low). Legal precepts, universally accepted, in the first 60 years for all countries interested in nuclear energy are being revised, then 20 years of experience. The civil responsibility limited is being questioned and indemnities updated. (author)

DOE's nuclear non-proliferation responsibilities are defined by the provisions of the Atomic Energy Act of 1954, as amended, and of the Nuclear Non-Proliferation Act of 1978 (NNPA). The Department's major responsibilities in this area are to: (1) provide technical assistance to the Department of State in negotiating agreements for civil cooperation in the peaceful uses of nuclear energy with other countries and international organizations; (2) join with other agencies to reach executive branch judgments with respect to the issuance of export licenses by the Nuclear Regulatory Commission; (3) be responsible for processing subsequent arrangements with other agencies as required by the Nuclear Non-Proliferation Act; (4) control the distribution of specialnuclear materials, components, equipment, and nuclear technology exports; (5) participate in bilateral and multilateral cooperation with foreign governments and organizations to promote the peaceful uses of nuclear energy; and (6) act as a primary technical resource with respect to US participation in the International Atomic Energy Agency

Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of specialnuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification.

Insurance for large nuclear installations covers mainly four types of risk: third party liability which in accordance with the nuclear conventions, is borne by a nuclear operator following an incident occurring in his installation or during transport of nuclear substances; material damage to the installation itself, which precisely is not covered by third party liability insurance; machinery breakdown, i.e. accidental damage or interruption of operation. Only the first category must be insured. In view of the magnitude of the risk, nuclear insurance resorts to co-insurance and reinsurance techniques which results in a special organisation of the nuclear insurance market, based on national nuclear insurance pools and on the Standing Committee on Atomic Risk of the European Insurance Committee. Conferences of the chairmen of nuclear insurance pools are convened regularly at a worldwide level. (NEA) [fr

This dictionary covers nuclear engineering defined in its general sense as applied nuclear physics: industrial and other applications of nuclear power, isotopes and ionizing radiation, nuclear materials, nuclear facilities and nuclear weapons together with their scientific and technological fundamentals. During the compilation of terms, great attention was only given to generally valid basic expressions and to special terms where these occurred in all four languages. A great number of textbooks and monographs, as well as specialist journals covering many years, have been evaluated. Detailed attention has been paid to standards. Of importance in nuclear engineering are the international standards of the International Atomic Energy Organization (including the terminology employed by the International Nuclear Information System INIS), the International Organization of Standardization, the Council for Mutual Economic Assistance, the World Energy Conference, the International Electrical Engineering Commission, and also a great many national standards which, unfortunately, frequently deviate from one another as regards definition and, in particular, designation. (orig.)

Arms control treaties, unilateral actions, and cooperative activities -- reflecting the defusing of East-West tensions -- are causing nuclear weapons to be disarmed and dismantled worldwide. In order to provide for future reductions and to build confidence in the permanency of this disarmament, verification procedures and technologies would play an important role. This paper outlines arms-control objectives, treaty organization, and actions that could be undertaken. For the purposes of this Workshop on Verification, nuclear disarmament has been divided into five topical subareas: Converting nuclear-weapons production complexes, Eliminating and monitoring nuclear-weapons delivery systems, Disabling and destroying nuclear warheads, Demilitarizing or non-military utilization of specialnuclear materials, and Inhibiting nuclear arms in non-nuclear-weapons states. This paper concludes with an overview of potential methods for verification

This work constitutes a summary of the research and development work made for the design and dimensioning of the canister for nuclear fuel disposal. Since the spent nuclear fuel disposal emits high temperature heats and much radiation, its careful treatment is required. For that, a long term(usually 10,000 years) safe repository for spent fuel disposal should be securred. Usually this repository is expected to locate at a depth of 500m underground. The canister construction type introduced here is a solid structure with a cast iron insert and a corrosion resistant overpack, which is designed for spent nuclear fuel disposal in a deep repository in the crystalline bedrock, which entails an evenly distributed load of hydrostatic pressure from undergroundwater and high pressure from swelling of bentonite buffer. Hence, the canister must be designed to withstand these high pressure loads. Many design variables may affect the structural strength of the canister. In this study, among those variables array type of inner baskets and thicknesses of outer shell and lid and bottom are tried to be determined through the mechanical linear structural analysis, thicknesses of outer shell is determined through the nonlinear structural analysis, and the bentonite buffer analysis for the rock movement is conducted through the of nonlinear structural analysis Also the thermal stress effect is computed for the cast iron insert. The canister types studied here are one for PWR fuel and another for CANDU fuel. 23 refs., 60 figs., 23 tabs. (Author)

The background of the uranium industry in Canada is described. Government policies with respect to ownership of the uranium mining industry, price stabilization, and especially reservation of sufficient supplies of nuclear fuels for domestic utilities, are explained. Canadian policy re nuclear exports and safeguards is outlined. (E.C.B.)

Apart from the special requirements of quality assurance in the production of components for the nuclear industry, in particular nuclear power stations, the author discusses special methods of quality control in the testing of welded joints. (TK) [de

This book contains the contributions presented during a one-day seminar. The authors propose a framework for a legal approach to nuclear safety, a discussion of the 2009/71/EURATOM directive which establishes a European framework for nuclear safety in nuclear installations, a comment on nuclear safety and environmental governance, a discussion of the relationship between citizenship and nuclear, some thoughts about the Nuclear Safety Authority, an overview of the situation regarding the safety in nuclear waste burying, a comment on the Nome law with respect to electricity price and nuclear safety, a comment on the legal consequences of the Fukushima accident on nuclear safety in the Japanese law, a presentation of the USA nuclear regulation, an overview of nuclear safety in China, and a discussion of nuclear safety in the medical sector

The aim of this French-English bilingual Guide is to present a synthesis embracing all the aspects and all the implications of the development of nuclear energy by situating it both within the French administrative and professional framework and in the world context. Special attention has been paid to the protection of man and the environment and to safety and security problems; most of the other questions -technological, economic, industrial- which arise at all points in the nuclear cycle. Teaching and research are outlined and a special appendix is devoted to nuclear information [fr

Removing the threat of a nuclear war-as the General Assembly formally stated in the Final Document of its first special session devoted to disarmament, in 1978-is considered to be the task of the present day. In that Document, the General Assembly sought to establish principles, guidelines and procedures for preventing nuclear war. It declared that to that end, it was imperative to remove the threat of nuclear weapons, to halt and reverse the nuclear-arms race until the total elimination of nuclear weapons and their delivery systems had been achieved (see chapter iv), and to prevent the proliferation of nuclear weapons (see chapter VII). At the same time, it called for other measures designed to prevent the outbreak of nuclear war and to lessen the danger of the treat or use of nuclear weapons. The Assembly's clear call for action was dictated by the awareness that there was no insuperable barrier dividing peace from war and that, unless nations brought the spiralling nuclear-arms race to an end, the day might come when nuclear weapons would actually be used, with catastrophic consequences. In adopting the Final Document, the international community achieved, for the first time, a consensus on an international disarmament strategy having as its immediate goal the elimination of the danger of a nuclear war and the implementation of measures to halt and reverse the arms race. The General Assembly, at its second special session on disarmament, in 1982, reaffirmed the validity of the 1978 Final Document. This paper reports that nuclear issues and in particular the prevention of nuclear war remain, however, major concerns of all States. Undoubtedly, all nations have a vital interest in the negotiation of effective measures for her prevention of nuclear war, since nuclear weapons pose a unique threat to human survival. If nuclear war were to occur, its consequences would be global, not simple regional

arbitrage strategy is characterized by specialization versus replication and argue that these different strategies may have differential impact on profitability and risk reduction. Developing a sophisticated measure of international specialization and using a unique panel data set of 92 German MNEs to test......Whether and how international diversification and cross-border arbitrage affects firm performance remains one of the major unresolved research questions in the strategy and international business literatures. We propose that knowing how much a firm has internationally diversified tells us very...... little about performance implications, if we do not know, and do not ask, how the firm has diversified. Therefore, building on the two broad arguments of operating flexibility and location-specific commitment, we develop a theoretical framework that focuses on the extent to which a firm's international...

Recent research in the area of nuclear level densities is reviewed. The current interest in nuclear astrophysics and in structure of nuclei off of the line of stability has led to the development of radioactive beam facilities with larger machines currently being planned. Nuclear level densities for the systems used to produce the radioactive beams influence substantially the production rates of these beams. The modification of level-density parameters near the drip lines would also affect nucleosynthesis rates and abundances

In his special lecture, given at the Artsimovich-Kadomtsev Memorial Session of the 17th IAEA Fusion Energy Conference in Yokohama, October 1998, Prof. H. Yoshikawa stated that the fusion program had come to a crossroads. He was wondering whether the future would lead to cooperation between nations, striving to overcome the difficulties the world is confronted with, or if it would lead to despair

Special offer for members of the Staff Association and their families 10% reduction on all products in the SEPHORA shop (sells perfume, beauty products etc.) in Val Thoiry ALL YEAR ROUND. Plus 20% reduction during their “vente privée”* three or four times a year. Simply present your Staff Association membership card when you make your purchase. * next “vente privée” from 24th to 29th May 2010

SPECIAL OFFER FOR OUR MEMBERS Tarif unique Adulte/Enfant Entrée Zone terrestre 19 euros instead of 23 euros Entrée “Zone terrestre + aquatique” 24 euros instead of 31 euros Free for children under 3, with limited access to the attractions. Walibi Rhône-Alpes is open daily from 22 June to 31 August, and every week end from 3 September until 31 October. Closing of the “zone aquatique” 11 September.

LMNA gene encodes for nuclear intermediate filament proteins lamin A/C. Mutations in this gene lead to a spectrum of genetic disorders, collectively referred to as laminopathies. Lamin A/C are widely expressed in most differentiated somatic cells but not in early embryos and some undifferentiated cells. To investigate the role of lamin A/C in cell phenotype maintenance and differentiation, which could be a determinant of the pathogenesis of laminopathies, we examined the role played by exogenous lamin A and its mutants in differentiated cell lines (HeLa, NHDF) and less-differentiated HEK 293 cells. We introduced exogenous wild-type and mutated (H222P, L263P, E358K D446V, and ∆50) lamin A into different cell types and analyzed proteins' impact on proliferation, protein mobility, and endogenous nuclear envelope protein distribution. The mutants give rise to a broad spectrum of nuclear phenotypes and relocate lamin C. The mutations ∆50 and D446V enhance proliferation in comparison to wild-type lamin A and control cells, but no changes in exogenous protein mobility measured by FRAP were observed. Interestingly, although transcripts for lamins A and C are at similar level in HEK 293 cells, only lamin C protein is detected in western blots. Also, exogenous lamin A and its mutants, when expressed in HEK 293 cells underwent posttranscriptional processing. Overall, our results provide new insight into the maintenance of lamin A in less-differentiated cells. Embryonic cells are very sensitive to lamin A imbalance, and its upregulation disturbs lamin C, which may influence gene expression and many regulatory pathways.

INIS: a worldwide hub where nuclear information is preserved, validated, and made universally available. Within this special edition of the Newsletter, celebrating the 45th birthday of INIS, you will probably read this definition, and many more, of the International Nuclear Information System. However, INIS has some special aspects, not immediately visible to those who interact with the System and the INIS Secretariat, which make it unique in the scientific environment. In this article, I will try to share my experience with INIS and the memories that have stayed with me, even after my departure. I joined INIS in 2006 as an IT Systems Engineer. I must say that I found a very complex IT infrastructure with over 20 servers and several software applications which, given the small size of the INIS Unit, clearly reflected the multitude of activities INIS was (and still is) involved in. From the start, I felt that INIS was perceived in a different way by other people involved with Information Technology. In fact, since its birth in 1970, INIS has proven to be extremely innovative and open to embracing new technologies, compared with other parts of the Agency. For example, Livelink was proposed and installed for the first time by the INIS Unit before becoming the IAEA standard tool for enterprise document management, and presently, is uniquely and sharply customized to fulfill INIS’ critical weekly task of processing thousands of bibliographic and full text records

The paper considers the question of synergy between nuclear safety and nuclear security. Special attention is paid to identifying interface of the two areas of safety and definition of common principles for nuclear security and nuclear safety measures. The principles of defense in depth, safety culture and graded approach are analyzed in detail.Specific features characteristic of nuclear safety and security are outlined

The effects of Ti and Ta addition on microstructure stability and tensile properties of a reduced activation ferritic/martensitic (RAFM) steel have been investigated. Ti addition of 0.06 wt% to conventional RAFM reference base steel (Fe-9.3Cr-0.93W-0.22V-0.094Ta-0.1C) was intended to promote the precipitation of nano-sized (Ti,W) carbides with a high resistance to coarsening. In addition, the Ti addition was substituted for 0.094 wt% Ta. The Ti-added RAFM steel (Ti-RAFM) exhibited a higher yield strength (ΔYS = 32 MPa) at 600 °C than the reference base steel due to additional precipitation hardening by (Ti,W)-rich MX with an average size of 6.1 nm and the area fraction of 2.39%. However, after thermal exposure at 600 °C for 1000 h, this Ti-RAFM was more susceptible to degradation than the reference base steel; the block width increased by 77.6% in Ti-RAFM after thermal exposure while the reference base steel showed only 9.1% increase. In order to suppress diffusion rate during thermal exposure, the large-sized Ta element with low activation was added to Ti-RAFM. The Ta-added Ti-RAFM steel exhibited good properties with outstanding microstructure stability. Quantitative comparison in microstructures was discussed with a consideration of Ti and Ta addition.

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Are you a member of the Staff Association? Did you know that as a member you can benefit from the following special offers: BCGE (Banque Cantonale de Genève): personalized banking solutions with preferential conditions. TPG: reduced rates on annual transport passes for active and retired staff. Aquaparc: reduced ticket prices for children and adults at this Swiss waterpark in Le Bouveret. Walibi: reduced prices for children and adults at this French attraction park in Les Avenières. FNAC: 5% reduction on FNAC vouchers. For more information about all these offers, please consult our web site: http://association.web.cern.ch/association/en/OtherActivities/Offers.html

The primary Facility Stabilization mission is to provide minimum safe surveillance and maintenance of facilities and deactivate facilities on the Hanford Site, to reduce risks to workers, the public and environment, transition the facilities to a low cost, long term surveillance and maintenance state, and to provide safe and secure storage of specialnuclear materials, nuclear materials, and nuclear fuel. Facility Stabilization will protect the health and safety of the public and workers, protect the environment and provide beneficial use of the facilities and other resources. Work will be in accordance with the Hanford Federal Facility Agreement and Consent Order (Tri-Party Agreement), local, national, international and other agreements, and in compliance with all applicable Federal, state, and local laws. The stakeholders will be active participants in the decision processes including establishing priorities, and in developing a consistent set of rules, regulations, and laws. The work will be leveraged with a view of providing positive, lasting economic impact in the region. Effectiveness, efficiency, and discipline in all mission activities will enable Hanford Site to achieve its mission in a continuous and substantive manner. As the mission for Facility Stabilization has shifted from production to support of environmental restoration, each facility is making a transition to support the Site mission. The mission goals include the following: (1) Achieve deactivation of facilities for transfer to EM-40, using Plutonium Uranium Extraction (PUREX) plant deactivation as a model for future facility deactivation; (2) Manage nuclear materials in a safe and secure condition and where appropriate, in accordance with International Atomic Energy Agency (IAEA) safeguards rules; (3) Treat nuclear materials as necessary, and store onsite in long-term interim safe storage awaiting a final disposition decision by US Department of Energy; (4) Implement nuclear materials

Commemorating the 30 year anniversary of commercial nuclear power plant operation in KOREA, Korea Hydro and Nuclear Power Co., Ltd. (KHNP) has conducted a Special Safety Review (SSR) of its 20 operating units to understand their safety performance and to identify any areas that need improvement. The SSR reviewed all 20 operating units for 2 weeks per site. Areas that were reviewed are Safety Margins, Plant Performance, Employee Safety, Employee Performance and Performance Improvement Process. Each review team consisted of international and domestic members. The international reviewers were from IAEA, WANO and INPO. The domestic reviewers consisted of professors, Engineering Company, Research Institute and KHNP experts. The review confirmed safe and reliable operations of the 20 nuclear units. The common understanding resulted from the SSR is as follows. Firstly, KHNP corporate and its plants confirmed and shared mutual understanding on recurring areas for improvements, especially in the areas of Organizational Effectiveness, Industrial Safety, Human Performance, Configuration Management, Operations, Equipment Performance and Material Condition. Secondly, KHNP understood that plant and department level performances are directly related to the leadership and competency of the management team including supervisors. Thirdly, the strengths of individual stations that consistently have produced good results need to be shared with the other KHNP stations. Finally, KHNP learned that strong corporate leadership and support are needed to resolve most of the areas for improvement since they are common to all KHNP stations. (author)

The properties of bicelles composed of mixtures of long-chain lipids dimyristoylphosphatidylcholine (DMPC) and dimyristoylphosphatidylglycerol (DMPG), stabilized by zwitterionic bile salt analogue 3-[(3-cholamidopropyl)dimethyl-d6-ammonio]-2-hydroxy-1-propanesulfonate (CHAPSO-d6), deuterated at both amino methyls, were investigated by a combination of (31)P and (2)H NMR, focusing on the behavior of CHAPSO as a function of temperature. For compositions of molar ratio q = [DMPC + DMPG]/[CHAPSO] = 3, R = [DMPG]/[DMPC + DMPG] = 0, 0.01 and 0.10 and lipid concentration CL = 25 wt % lipid at temperatures of between 30 and 60 °C, magnetic alignment was readily achieved as assessed via both (31)P NMR of the phospholipids and (2)H NMR of CHAPSO-d6. Increasing temperature yielded higher values for the chemical shift anisotropy of the former and the quadrupole splitting of the latter, consistent with the progressive migration of CHAPSO from edge regions into planar regions of the bicellar assemblies. However, relative to dihexadecyl phosphatidylcholine (DHPC), CHAPSO exhibited lower miscibility with DMPC, although the presence of DMPG enhanced this miscibility. At 65 °C, thermal instability became evident in the appearance of a separate isotropic component in both (31)P and (2)H NMR spectra. This isotropic phase was CHAPSO-enriched but less so as a function of increasing DMPG. These findings indicate that the enhanced thermal stability of CHAPSO- versus DHPC-containing bicelles arises from a combination of the larger surface area that edge CHAPSO is able to mask, mole for mole, and its relative preference for edge regions, plus, possibly, specific interactions with DMPG.

After an historical overview of the nuclear regulation system in Argentina a description is made of the country's Nuclear Regulatory Authority (ARN) and of its regulation and control functions. Its organic structure is also outlined. A detailed report is given of the environmental monitoring activities in the sites of the operating Argentine nuclear power plants as well as those of the nuclear research centres. A special reference is made of the monitoring of the relevant uranium mining districts in Argentina. The radon determination in houses of several regions of the country is also mentioned

This study addresses the utility of, and need for, nuclear weapons a decade after the end of the Cold War with special focus on the numbers and types of nuclear weapons appropriate for particular requirements...

This Environmental Development Plan includes the process steps and facilities necessary for the production of plutonium and tritium for Government needs and the production of some other radioactive materials that will be used for heat and radiation sources by domestic and international customers. The production reactors and the spent fuel processing plants and their effluents are discussed, but the defense wastes from them are treated in a separate EDP. The scope does not include transportation, decontamination and decommissioning, safeguards and security, or use of the SNM products

In support of the Department of Energy's Dismantlement Program, the Optoelectronics Characterization and Sensor Development Department 2231 at Sandia National Laboratories/New Mexico has developed an in situ nonintrusive Optoelectronic Inventory System (OIS) that has the potential for application wherever periodic inventory of selected material is desired. Using a network of fiber-optic links, the OIS retrieves and stores inventory signatures from data storage devices (which are permanently attached to material storage containers) while inherently providing electromagnetic pulse immunity and electrical noise isolation. Photovoltaic cells (located within the storage facility) convert laser diode optic power from a laser driver to electrical energy. When powered and triggered, the data storage devices sequentially output their digital inventory signatures through light-emitting diode/photo diode data links for retrieval and storage in a mobile data acquisition system. An item's exact location is determined through fiber-optic network and software design. The OIS provides an on-demand method for obtaining acceptable inventory reports while eliminating the need for human presence inside the material storage facility. By using modularization and prefabricated construction with mature technologies and components, an OIS installation with virtually unlimited capacity can be tailored to the customer's requirements

The special actinide nuclides such as Np, Cm, etc. which are produced as byproducts during the operation of fission reactors are presently looked upon as 'nuclear waste' and are proposed to be disposed of as part of high level waste in deep geological repositories. The potential hazard posed to future generations over periods of thousands of years by these long lived nuclides has been a persistent source of concern to critics of nuclear power. However, the authors have recently shown that each and every one of the special actinide nuclides is a better nuclear fuel than the isotopes of plutonium. This finding suggests that one does not have to resort to exotic neutron sources for transmuting/incinerating them as proposed by some researchers. Recovery of the special actinide elements from the waste stream and recycling them back into conventional fission reactors would eliminate one of the stigmas attached to nuclear energy

The fifth brief in the series about special operations highlights the possible strategic role of special operations in connection with Denmark's revitalized vision of integration of the state's instruments to create security through preventive stabilization efforts. The brief offers suggestion...... on tangible operationalization of this vision and provides knowledge on how special operations can be an attractive instrument in comprehensive conflict prevention, including how the special characteristics of special operations make them suitable for supporting the non-military instruments....

This book offers an essential bridge between college-level introductions and advanced graduate-level books on special relativity. It begins at an elementary level, presenting and discussing the basic concepts normally covered in college-level works, including the Lorentz transformation. Subsequent chapters introduce the four-dimensional worldview implied by the Lorentz transformations, mixing time and space coordinates, before continuing on to the formalism of tensors, a topic usually avoided in lower-level courses. The book’s second half addresses a number of essential points, including the concept of causality; the equivalence between mass and energy, including applications; relativistic optics; and measurements and matter in Minkowski spacetime. The closing chapters focus on the energy-momentum tensor of a continuous distribution of mass-energy and its covariant conservation; angular momentum; a discussion of the scalar field of perfect fluids and the Maxwell field; and general coordinates. Every chapter...

Are you a member of the Staff Association? Did you know that as a member you can benefit from the following special offers: BCGE (Banque Cantonale de Genève): personalized banking solutions with preferential conditions. TPG: reduced rates on annual transport passes for active and retired staff. Aquaparc: reduced ticket prices for children and adults at this Swiss waterpark in Le Bouveret. Walibi: reduced prices for children and adults at this French attraction park in Les Avenières. FNAC: 5% reduction on FNAC vouchers. For more information about all these offers, please consult our web site: http://association.web.cern.ch/association/en/OtherActivities/Offers.html

Are you a member of the Staff Association? Did you know that as a member you can benefit from the following special offers: BCGE (Banque Cantonale de Genève): personalized banking solutions with preferential conditions. TPG: reduced rates on annual transport passes for all active and retired staff. Aquaparc: reduced ticket prices for children and adults at this Swiss waterpark in Le Bouveret. Walibi: reduced prices for children and adults at this French attraction park in Les Avenières. FNAC: 5% reduction on FNAC vouchers. For more information about all these offers, please consult our web site: http://association.web.cern.ch/association/en/OtherActivities/Offers.html

A special wide-load convoy will affect traffic between Hall 180 (Meyrin site) and Point 1 (ATLAS) on Tuesday 29 May. The following measures will be in place: Partial closure of Route Arago and Route Einstein between 9.00 a.m. and 12 midday, depending on the rate at which the convoy advances. Closure of Route Einstein between 12 and 2.00 p.m. between Building 104 and Route Veksler (see diagram). Closure of Entrance B in both directions between 12 and 2.30 p.m. Please use Entrance A. For safety reasons, cyclists and pedestrians will not be allowed to ride or walk alongside the convoy. Please comply with the instructions given by the convoy officers. TS-IC Group (tel : 160319 - 163012)

This book is an introduction to special relativity theory. After a discussion of the limits of Newton's mechanics and the pecularities in the propagation of light the Lorentz transformation is introduced. Then the measurement of space and time intervals in the framework of relativity theory is considered. Thereafter the addition of velocities and acceleration are considered in this framework. Then relativistic kinematics of particle interactions are described. Then the four-dimensional calculus in space-time coordinates is introduced. Finally an introduction is given to the treatment of the electromagnetic field in the framework of relativity theory. Every chapter contains exercise problems with solutions. This book is suited for all students who want to get some fundamental knowledge about relativity theory. (HSI) [de

Stabilization of enzymes is a key factor when using biocatalysis in practice. Each enzyme stability depends both on the structure of its molecule and on the effect of various environmental factors, thus, one of the methods of the enzyme stability preservation is the formation of optimal macromedium. Thus, water structure and enzyme hydration change in the presence of solvable additives that affects its stability and catalytic properties. The paper deals with a new method of stabilization of human thrombin developed by the authors. It is proposed to use some known organic-ligands which have ion group and different nonpolar hydrophobic groups instead of traditional additives (salts, aminoacids, polyols, polyethylene glycols etc.). Thrombin stabilization proceeds in the conditions something changed compared with traditional ones. Processes of thrombin stabilization by the above compound have been investigated, enzyme stability at different temperatures and long-term storage of diluted solutions of the preparation in different conditions have been studied. It has been established that rosselin and orange II are the most efficient ligands. Optimal finite concentrations of stabilizing agents make approximately 0.0012-0.0014 M which are rather low in the system thrombin-ligand. It has been found that diluted solutions of thrombin are more stable, than concentrated ones. In the latter case the process of autolysis is included that affects negatively the catalytic effect of the enzyme, as far as there occurs the change of thrombin molecule structure, especially of thrombin beta-chain sections, evoking conformational changes of some sites of its active centre. The experiments directed to increasing thrombin intensity in the presence of organic ligands rosselin and orange II are discussed in details. Special attention is given to autolytic method of thrombin inactivation. It is admitted on the basis of already obtained data that thrombin binding with organic ligands proceeds

The present study deals with the molecular mechanisms involved in the regulation of E-cadherin expression under hypoxia, because the adjustment of the amount of E-cadherin due to physical stimuli of the microenvironment might influence the colonization of metastasis to skeleton. We analyzed the effect of 1% oxygen tension, that is similar to that encountered in the bone marrow by metastatic cells spreading from breast carcinoma. The purpose was to evaluate the hypoxia-orchestrated control of E-cadherin transactivation via hypoxia inducible factor-1 (HIF-1) and peroxisome proliferator activated receptor-γ (PPARγ), and the involvement of Hippo pathway members, as regulators of transcription factors. To give a translational significance to the study, we took into consideration human pair-matched ductal breast carcinoma and bone metastasis: E-cadherin and Wwox were expressed in bone metastasis but not in breast carcinoma, while HIF-1α and TAZ seemed localized principally in nuclei of metastasis and were found in all cell compartments of breast carcinoma. A close examination of the regulatory mechanisms underlying E-cadherin expression in bone metastasis was done in 1833 clone derived from MDA-MB231 cells. Hypoxia induced E-cadherin only in 1833 clone, but not in parental cells, through HIF-1 and PPARγ activities, while Wwox decreased. Since Wwox was highly expressed in bone metastasis, the effect of ectopic Wwox was evaluated, and we showed E-cadherin transactivation and enhanced invasiveness in WWOX transfected 1833 cells. Also, hypoxia was additive with ectopic Wwox remarkably enhancing HIF-1α nuclear shuttle and accumulation due to the lengthening of the half-life of HIF-1α protein; under this experimental condition HIF-1α appeared as a slower migrated band compared with control, in agreement with the phosphorylation state. The in vitro data strongly supported the almost exclusive presence of HIF-1α in nuclei of human-bone metastasis. Thus, we identified

Dr. Chandrasekhar's book received high praise when it first appeared in 1961 as part of Oxford University Press' International Series of Monographs on Physics. Since then it has been reprinted numerous times in its expensive hardcover format. This first lower-priced, sturdy paperback edition will be welcomed by graduate physics students and scientists familiar with Dr. Chandrasekhar's work, particularly in light of the resurgence of interest in the Rayleigh-Bénard problem. This book presents a most lucid introduction to the Rayleigh-Bénard problem: it has also been applauded for its thorough, clear coverage of the theory of instabilities causing convection. Dr. Chandrasekhar considers most of the typical problems in hydromagnetic stability, with the exception of viscous shear flow; a specialized domain deserving a book unto itself. Contents include: Rotation; Stability of More General Flows; Bénard Problem; Gravitational Equilibrium and Instability; Stability of a Magnetic Field; Thermal Instability of a L...

Numerous workers have participated in recovery efforts following the accident that occurred at the Tokyo Electric Power Company (TEPCO) Fukushima Daiichi Nuclear Power Plant after the Great East Japan Earthquake. These workers, belonging to various companies, have been engaged in various tasks since the accident. Given the hazards and stress involved in these tasks and the relatively long time required to transport sick or injured workers to medical institutions, it became necessary to quickly implement a more stringent management program for fitness for duty than in ordinary work environments. It took considerable time to introduce and improve a fitness-for-duty program because of several concerns. Various efforts were conducted, sometimes triggered by guidance from the Ministry of Health, Labour and Welfare (MHLW), but the implementation of the program was insufficient. In April 2016, a new program was initiated in which all primary contractors confirmed that their subcontractors had achieved five conditions for workers' fitness for duty on the basis of guidance from the MHLW and occupational health experts. TEPCO confirmed that all primary contractors had implemented the program successfully as of the end of November 2016. Following a disaster, even though the parties concerned understand the necessity of fitness-for-duty programs and that companies in high positions have responsibilities beyond their legal requirements, it is highly possible that they may hesitate to introduce such programs without guidance from the government. It is necessary to prepare a governmental framework and professional resources that introduce these stringent management programs quickly.

The 'Mina Fe' U deposit (Salamanca, Spain) has been studied in the context of Enresa's programme for U-mine sites restoration and also as a natural analogue for processes in high-level nuclear waste (HLNW) geological disposal. The investigations encompassed an array of geoscience disciplines, such as structural geology, mineralogy, hydrogeology and elemental and isotopic geochemistry and hydrogeochemistry of the site. Based on the obtained results, a conceptual mineralogical and geochemical model was performed integrating the main geochemical processes occurring at the site: the interaction between oxidised and slightly acidic water with pyrite, pitchblende, calcite and dolomite, as essential minerals of the U fracture-filling mineralisation, and hydroxyapatite from the host rock, as the main source of P. This conceptual model has been tested in a systematic numerical model, which includes the main kinetic (pyrite and pitchblende dissolution) and equilibrium processes (carbonate mineral dissolution, and goethite, schoepite and autunite secondary precipitation). The results obtained from the reactive-transport model satisfactorily agree with the conceptual model previously established. The assumption of the precipitation of coffinite as a secondary mineral in the system cannot be correctly evaluated due to the lack of hydrochemical data from the reducing zone of the site and valid thermodynamic and kinetic data for this hydrated U(IV)-silicate. This precipitation can also be hampered by the probable existence of dissolved U(IV)-organic matter and/or uranyl carbonate complexes, which are thermodynamically stable under the alkaline and reducing conditions that prevail in the reducing zone of the system. Finally, the intense downwards oxic and acidic alteration in the upper part of the system is of no relevance for the performance assessment of a HLNW disposal. However, the acidic and oxidised conditions are quickly buffered to neutral-alkaline and reducing at very

All the objectives originally scheduled for the first year of this grant have been achieved. Furthermore, the project is ahead of schedule, in that a substantial amount of work has been completed on two significant objectives originally planned for the second year. This interim report is divided into five parts, summarizing the mathematical development, analysis and results of the project goals -- goals originally planned for the first year and completed, and those on which substantial progress has been made ahead of schedule. Effects of unheated riser sections and the downcomer recirculation loop on the stability characteristics of advanced boiling water reactor designs that incorporate risers or unheated channel extensions are summarized in Part A. Such extensions are incorporated above the heated reactor core channels to enhance buoyancy-driven natural thermal convection both during normal at-power operation and during emergency shutdown. The effects of both, the inclusion of unheated riser sections in the designs (one of the goals substantially completed ahead of schedule), and the inclusion of the recirculation loop in the models (first year goal) were generally found to be destabilizing. In general, as riser lengths were increased equilibria that previously were stable became unstable, and the systems with the taller risers evolved to density-wave limit cycle oscillations. As a building block of the second year goal -- to extend the one dimensional dynamical analysis of reactor thermal-hydraulics/neutron-kinetics to two and three dimensions -- we have carried out, ahead of schedule, the nonlinear dynamical analysis of two-phase flow in multiple parallel heated channels. Some basic aspects of bifurcation phenomena in two-phase flow and the related nonlinear dynamics of single and multiple parallel, uniformly and nonuniformly heated channels are studied

Special discount to the members of the Staff Association Aquaparc Discounted prices on admission of whole day. Children from 5 to 15 years: 26.– CHF instead of 35.– CHF; Adults from 16 years: 32.– CHF instead of 43.– CHF.Tickets on sale to the Staff Association Secretariat. BCGE Account management on salary account and annual subscription to credit cards free of charge. Other benefits on mortgage loan and financial planning. Comédie de Genève 20% off on full price tickets (also available for partner): from 24 to 32 CHF a ticket instead of 30 to 40 CHF depending on the shows. Ezee Suisse 15% off on the range of electric bikes upon presentation of your Staff Association membership card before payment. FNAC 5% discount on gifts card available in four Swiss shops without any restriction. Gifts card on sale to the Staff Association Secretariat. FutureKids 15% off for the Staff Association members who enrol their children of 5 to 16 years old in ...

Molybdenum solubility is a limiting factor to actinide loading in nuclear waste glasses, as it initiates the formation of water-soluble crystalline phases such as alkali molybdates. To increase waste loading efficiency, alternative glass ceramic structures are sought that prove resistant to internal radiation resulting from radioisotope decay. In this study, selective formation of water-durable CaMoO 4 in a soda lime borosilicate is achieved by introducing up to 10 mol % MoO 3 in a 1:1 ratio to CaO using a sintering process. The resulting homogeneously dispersed spherical CaMoO 4 nanocrystallites were analyzed using electron microscopy, X-ray diffraction (XRD), Raman and electron paramagnetic resonance (EPR) spectroscopies prior to and post irradiation, which replicated internal β-irradiation damage on an accelerated scale. Following 0.77 to 1.34 GGy of 2.5 MeV electron radiation CaMoO 4 does not exhibit amorphization or significant transformation. Nor does irradiation induce glass-in-glass phase separation in the surrounding amorphous matrix, or the precipitation of other molybdates, thus proving that excess molybdenum can be successfully incorporated into a structure that it is resistant to β-irradiation proportional to 1000 years of storage without water-soluble byproducts. The CaMoO 4 crystallites do however exhibit a nonlinear Scherrer crystallite size pattern with dose, as determined by a Rietveld refinement of XRD patterns and an alteration in crystal quality as deduced by anisotropic peak changes in both XRD and Raman spectroscopy. Radiation-induced modifications in the CaMoO 4 tetragonal unit cell occurred primarily along the c-axis indicating relaxation of stacked calcium polyhedra. Concurrently, a strong reduction of Mo 6+ to Mo 5+ during irradiation is observed by EPR, which is believed to enhance Ca mobility. These combined results are used to hypothesize a crystallite size alteration model based on a combination of relaxation and diffusion

The following topics are discussed in 5 chapters: nuclear power, nuclear fuel cycle, radioactive waste management, special events, highlights of the IAEA's work. In the field of nuclear power, the status of nuclear energy generation at the end of 1990 is presented, as well as power plant performance, nuclear power costs, power plant aging and life extension, advanced reactor systems, quality management and quality assurance, automation and human action in nuclear power plant operation and finally the trends of nuclear power to 2010. The following aspects concerning nuclear fuel cycle are discussed: uranium exploration, resources, supply and demand, refining and conversion, enrichment, reactor fuel technology, spent fuel management, economics of the nuclear fuel cycle and trends for the near future. In the field of radioactive waste management, problems concerning treatment and conditioning of radioactive waste, radioactive waste disposal, decontamination and decommissioning and trends for the near future are discussed. Refs, figs and tabs

This book consists of 14 chapters which are CNN era and big science, from East and West to North and South, illusory nuclear strategy, UN and nuclear arms reduction, management of armaments, advent of petroleum period, the track of nuclear power generation, view of energy, internationalization of environment, the war over water in the Middle East, influence of radiation and an isotope technology transfer and transfer armament into civilian industry, the end of nuclear period and the nuclear Nonproliferation, national scientific and technological power and political organ and executive organ.

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We present method for the improvement of the measurement accuracy in the optical frequency spectra measurements based on tunable optical filters. The optical filter was used during the design and realization of the measurement system for the inspection of the fiber Bragg gratings. The system incorporates a reference block for the compensation of environmental influences, an interferometric verification subsystem and a PC - based control software implemented in LabView. The preliminary experimental verification of the measurement principle and the measurement system functionality were carried out on a testing rig with a specially prepared concrete console in the UJV Řež. The presented system is the laboratory version of the specialnuclear power plant containment shape deformation measurement system which was installed in the power plant Temelin during last year. On the base of this research we started with preparation other optical fiber sensors to nuclear power plants measurement. These sensors will be based on the microstructured and polarization maintaining optical fibers. We started with development of new methods and techniques of the splicing and shaping optical fibers. We are able to made optical tapers from ultra-short called adiabatic with length around 400 um up to long tapers with length up to 6 millimeters. We developed new techniques of splicing standard Single Mode (SM) and Multimode (MM) optical fibers and splicing of optical fibers with different diameters in the wavelength range from 532 to 1550 nm. Together with development these techniques we prepared other techniques to splicing and shaping special optical fibers like as Polarization-Maintaining (PM) or hollow core Photonic Crystal Fiber (PCF) and theirs cross splicing methods with focus to minimalize backreflection and attenuation. The splicing special optical fibers especially PCF fibers with standard telecommunication and other SM fibers can be done by our developed techniques. Adjustment

The underlying structure in the region A ∼ 100, N ∼ 60 has been under intensive and extensive investigation, mainly by β-decay and γ-ray spectroscopy from fission processes. Around N ∼ 60, by adding just few neutrons, protons a rapid shape change occurs from spherical-like to well deformed g.s. shape. Shape coexistence has been observed in the Sr and Zr nuclei, and is expected to take place in the whole region. The mechanisms involved in the appearance of the deformation is not well understood. The interplay between down-sloping and up-sloping neutron Nilsson orbital is evoked as one of the main reasons for the sudden shape change. However, a clear identification of the active proton and neutron orbitals was still on-going. For that purpose, the neutron rich 93;95;97;99 Rb isotopes have been studied by Coulomb excitation at CERN (ISOLDE) using the REX-ISOLDE post-accelerator and the MINIBALL setup. The completely unknown structures of 97;99 Rb have been populated and observed. Prompt γ-ray coincidences of low-lying states have been observed and time-correlated in order to build level schemes. The associated transition strengths have been extracted with the GOSIA code. The observed matrix elements of the electromagnetic operator constituted new inputs of further theoretical calculations giving new insight on the involved orbitals. The sensitivity of such experiment can be increased using nuclear spin polarized radioactive ion beam. For that purpose the Tilted Foils Technique (TFT) of polarization has been investigated at CERN. This technique consists to spin polarize the ion beam, passing through thin foils tilted at an oblique angle with respect to the beam direction. The initially obtained atomic polarization is transferred to the nucleus by hyperfine interaction. This technique does not depend on the chemical nature of the element. Short lived nuclei can be polarized in-flight without any need to be stopped in a catcher. It opens up the possibility to

Nuclear fuel supply is viewed as a buyer's market of assured medium-term stability. Even on a long-term basis, no shortage is envisaged for all conceivable expansion schedules. The conversion and enrichment facilities developed since the mid-seventies have done much to stabilize the market, owing to the fact that one-sided political decisions by the USA can be counteracted efficiently. In view of the uncertainties concerning realistic nuclear waste management strategies, thermal recycling and mixed oxide fuel elements might increase their market share in the future. Capacities are being planned accordingly. (orig.) [de

The Nuclear Physics group at UTK is involved in heavy-ion physics including both nuclear structure and reaction mechanisms. During the last year experimental work has been in 3 broad areas: structure of nuclei at high angular momentum, structure of nuclei far from stability, and ultra-relativistic heavy-ion physics. Results in these areas are described in this document under: properties of high-spin states, study of low-energy levels of nuclei far from stability, and high-energy heavy-ion physics (PHENIX, etc.). Another important component of the work is theoretical interpretation of experimental results (Joint Institute for Heavy Ion Research)

Some general and some critical remarks on: nuclear energy as an image for politics; nuclear energy as a model for research planning; nuclear controversy; the principle of precaution in nuclear and radiation protection law; reactor safety on probation; advantages and economy of nuclear energy; communication difficulties; the special role of nuclear energy; the need for European site planning; supervision of fissionable materials; the world's energy household in danger; global structure politics and nuclear energy; nuclear energy with a capacity for social innovations. (HP/LN) [de

A system is described for encapsulating spent nuclear fuel discharged from nuclear reactors in the form of rods or multi-rod assemblies. The rods are completely and contiguously enclosed in concrete in which metallic fibres are incorporated to increase thermal conductivity and polymers to decrease fluid permeability. This technique provides the advantage of acceptable long-term stability for storage over the conventional underwater storage method. Examples are given of suitable concrete compositions. (UK)

Theories of nuclear structure, stability, and radioactivity; nuclear reactions including fission, fusion, and reactors; and the applications of radioactivity, are covered. A non-mathematical treatment of the higher concepts are presented. The use of SI units, with cgs equivalents and ample clarifications in the form of worked examples; original examples investigated by the author in the applications of radioactivity; and selected problems are included